| |
Documents from the Job Database |
33.pdf |
| |
Documents from the Research Database |
35.pdf |
| |
List of Documents on ACEFAX |
36.pdf |
| |
Documents from the Third Internationl
Workshop on Implementation of ALARA at Nuclear Power Plants |
37.pdf |
| |
BNL ALARA Center Reports |
38.pdf |
| |
Enhancing ALARA and Reducing Costs:
The Future of Robotics |
39.pdf |
| |
Prevention of Heat Stress During
Radiological Work |
41.pdf |
| |
Article: Korea goes as low as
reasonably achievable |
42.pdf |
| |
Article: ALARA Center promotes good
practice in the USA |
43.pdf |
| |
Recommendations Concerning the
Reduction in the Use of Respirators |
44.pdf |
| |
A Questionnaire on Heat Stress |
45.pdf |
| |
Utility Radiological Protection
Contact Listing |
46.pdf |
| H-138 |
Innovative Approaches at TMI-2 |
138.pdf |
| H-175 |
A Method for Optimizing the Use of
Respiratory Protection in Radiation Areas |
175.pdf |
| H-176 |
Indian Point 2 Sub-system
Decontaminations |
176.pdf |
| H-177 |
National Demonstration of a Full RCS
Chemical Decontamination |
177.pdf |
| H-178 |
Plant E.I. Hatch Chemical Decon 1991 |
178.pdf |
| H-179 |
Chemical Decontamination of the
Residual Heat Removal System |
179.pdf |
| H-180 |
Ontario Hydro Decontamination
Experience |
180.pdf |
| H-181 |
Resource Management as an ALARA Tool |
181.pdf |
| H-182 |
PWR Upper/Lower Internals Shield |
182.pdf |
| H-183 |
Internal Dose, Respirator Protection
and Revised 10CFR20 at Davis-Besse Nuclear Power Station |
183.pdf |
| H-184 |
Zion Unit 2 Cycle 12 Shutdown and
Early Boration Results |
184.pdf |
| H-185 |
Health Physics Services on the
Platform at Salem Using ROMMRS |
185.pdf |
| H-186 |
Chemical Decon of Systems: Results and
Problems |
186.pdf |
| H-187 |
An Automated Program Implementing New
10CFR20 Requirements at Southern Nuclear Plants |
187.pdf |
| H-188 |
Steam Generator Replacement Project at
North Anna Power Station |
188.pdf |
| H-189 |
ALARA Programme Management and
Organization in EDF Nuclear Power Stations |
189.pdf |
| H-190 |
Enhanced Radiation Worker Training at
James A. Fitzpatrick Nuclear Plant |
190.pdf |
| H-191 |
S/G Replacement at Beznau 1:
Experience and Results in Radiological Protection |
191.pdf |
| H-192 |
Partners in Performance: An ALARA
Perspective |
192.pdf |
| H-193 |
Steam Generator Snubber Elimination |
193.pdf |
| H-194 |
Future Power Stations in the United
Kingdom Designing for Low Doses |
194.pdf |
| H-195 |
A Team Approach for the Management of
Radioactive Liquid Effluents |
195.pdf |
| H-196 |
ALARA and Work Management |
196.pdf |
| H-197 |
Radiological Assessment of
Decommissioning at Fort St. Vrain |
197.pdf |
| H-198 |
Personnel Radiation Exposure Reduction
During Remote Stud Handling at Indian Point 2 |
198.pdf |
| H-199 |
Replacement of RWCU Piping with
State-of-the-Art Materials |
199.pdf |
| H-200 |
Evaluation of Zircaloy Fuel Clad
Oxidation at Millstone 3 PWR |
200.pdf |
| H-201 |
An Update on Chemistry Related Dose
Reduction Efforts at Millstone Nuclear Generating Stations |
201.pdf |
| H-202 |
Surface Characterization of the Steam
Generator Channel Head Following Mechanical/Electropolishing at
Millstone Point Unit 2 |
202.pdf |
| H-203 |
Chromium Treatment of RHR Piping |
203.pdf |
| H-204 |
On-Line Monitoring of Dose Rates and
Surface Activity During the Cycle 17 Shutdown of Ringhals 2 |
204.pdf |
| H-205 |
Corrosion Products Behavior in French
Pressurized Water Reactor During Shutdown Operation |
205.pdf |
| H-206 |
PWR Startup and Shutdown Chemistry
Guidelines |
206.pdf |
| H-207 |
Update on Dose Rates in
Siemens-designed PWRs |
207.pdf |
| H-208 |
Dose Rate Trends and Chemistry at
Siemens-designed BWRs |
208.pdf |
| H-209 |
Industry Experience with Discrete
Radioactive Particles (DRP) |
209.pdf |
| H-210 |
Skin Injuries from Discrete
Radioactive Particles (DRP) |
210.pdf |
| H-211 |
Maintenance Productivity Aids for
Reactor Coolant and Recirculation Pump Seal Maintenance |
211.pdf |
| H-212 |
Utility Experience With Major
Radiation Monitoring System (RMS) Upgrades |
212.pdf |
| H-213 |
A Reusable Pouch for Enhancing Safety
and Radiation Protection at Oyster Creek |
213.pdf |
| H-214 |
Nuclear Power Plant Applications of
Bar Codes and Other Automatic Identification Technologies |
214.pdf |
| H-215 |
Maintenance Job Cards |
215.pdf |
| H-216 |
Infrared Thermography Gude (Revision
2) |
216.pdf |
| H-217 |
Assessment of Effective Dose
Equivalent for External Photon Radiation |
217.pdf |
| H-218 |
Total Worker Risk Minimization |
218.pdf |
| H-219 |
Assessment of Future Role of Radiation
Protection |
219.pdf |
| H-220 |
Preventive Measures for Radiation
Injury Litigation |
220.pdf |
| H-221 |
Effects of Respirators on Worker
Efficiency |
221.pdf |
| H-222 |
Analysis of Radiation Protection
Trends in the Nuclear Power Industry |
222.pdf |
| H-223 |
Permanent Shielding Design and
Installation for Dresden Unit 2 |
223.pdf |
| |
|
325.pdf |
| R-378 |
Elomix: A Better Way of Handling the
Waste from Decontamination |
378.pdf |
| J1 |
Replacement of Waste Collector Filter
Septa |
501.pdf |
| J2 |
Welding and Inspection of Pressurizer |
502.pdf |
| J7 |
Core Grid Support Repair |
507.pdf |
| J10 |
Turning Vanes Replacement |
510.pdf |
| J11 |
Decontamination of RWCU Using the Cord
Process |
511.pdf |
| J12 |
Feedwater Sparger Replacement |
512.pdf |
| J13 |
Work Inside Reactor Vessel |
513.pdf |
| J14 |
Vacuum Cleaning of Steam Generators |
514.pdf |
| J15 |
Decontamination of Primary Coolant
Pumps |
515.pdf |
| J16 |
Replacement of Incore Monitors |
516.pdf |
| J17 |
Desludging and Decontamination of
Radwaste Aisles |
517.pdf |
| J18 |
Installation of Insulation Cartridges |
518.pdf |
| J19 |
Shot Peening of the Hot Leg Tubes of a
Steam Generator |
519.pdf |
| J20 |
Shipment of Spent Fuel Assemblies |
520.pdf |
| J21 |
Radiation Protection Surveys and Job
Coverage |
521.pdf |
| J22 |
Replacement of a Pump in a High
Radiation Area |
522.pdf |
| J23 |
Insulation Replacement on
Recirculation Piping and Valves |
523.pdf |
| J24 |
Replacement of Insulation on Main
Steam Piping |
524.pdf |
| J25 |
Removing Scaffolding from Drywell |
525.pdf |
| J28 |
Repair of Main Steam Sensing Line
Supports |
528.pdf |
| J29 |
Replacement of Steam Generators |
529.pdf |
| J30 |
Replacement of Primary Pipes Inside
Containment |
530.pdf |
| J31 |
Shot Peening of the Cold Leg Tube of
Steam Generator |
531.pdf |
| J32 |
Up-Flow Conversion |
532.pdf |
| J33 |
Additional Experience from Shot
Peening |
533.pdf |
| J35 |
Decontamination of the Drywell |
535.pdf |
| J36 |
Valve Repair in Reactor Water Cleanup
System |
536.pdf |
| J37 |
Repair of Tube Bellows Flange |
537.pdf |
| |
|
538.pdf |
| D17 |
Reprocessing Waste to be Vitrified at
Karlsruhe |
817.pdf |
| R-333 |
BWR Underwater Disassembly/Assembly -
Wetlift 2000 |
1333.pdf |
| R-334 |
PWR Primary System Chemistry:
Experience with Elevated pH at Millstone Point Unit 3 |
1334.pdf |
| R-335 |
Steam Generator Dose Rates at Babcock
& Wilcox Reactors |
1335.pdf |
| R-336 |
Preconditioning of PWR Steam
Generators to Reduce Radiation Buildup |
1336.pdf |
| R-337 |
Welding of Norem Iron-Base Hardfacing
Alloy Wire Products - Procedures for Gas Tungsten Arc Welding |
1337.pdf |
| R-338 |
Endurance Tests of Valves with
Cobalt-Free Hardfacing Alloys |
1338.pdf |
| R-339 |
Replacement of Pins and Rollers in
Irradiated BWR Control Blades |
1339.pdf |
| R-340 |
Secondary Hydriding of Defected
Zircaloy-Clad Fuel Rods |
1340.pdf |
| R-341 |
Testing of an Organic Removal Process
in BWR Radwaste Systems |
1341.pdf |
| R-342 |
Evaluation of Reactor Pressure Vessel
Head Cracking in Two Domestic BWRs |
1342.pdf |
| R-343 |
Relationship of Radiation-Induced
Segregation Phenomena to Irradiation-Assisted Stress Corrosion Cracking
(IASCC) |
1343.pdf |
| R-344 |
Light Water Reactor Materials and
Water Chemistry Studies at Halden |
1344.pdf |
| R-345 |
PWR In-Pile Loop Studies in Support of
Coolant Chemistry Optimization |
1345.pdf |
| R-346 |
The Effect of Dissolved Oxygen in
Lithiated Coolant |
1346.pdf |
| R-347 |
Chemistry Parameters Influencing the
Dose Rate Build-up in BWR Plants |
1347.pdf |
| R-348 |
Overview of Activities for the
Reduction of Dose Rates in Swiss Boiling Water Reactors |
1348.pdf |
| R-349 |
Operating Experience of Japanese
Improvement and Standardization BWRs and Behavior of Radioactivity in
Reactor Water |
1349.pdf |
| R-350 |
Feedwater Iron Crud Reduction for
Chinshan Nuclear Power Station |
1350.pdf |
| R-351 |
Reactions of Iron Crud with Metallic
Ions Under BWR Water Conditions |
1351.pdf |
| R-352 |
Decomposition of Hydrogen Peroxide in
BWR Coolant Circuit |
1352.pdf |
| R-353 |
Full Primary System Chemical
Decontamination Qualification Program |
1353.pdf |
| R-354 |
Full System Decontamination and
Countermeasures Against Recontamination of the Fugen Nuclear Power
Station |
1354.pdf |
| R-355 |
Electrochemical Corrosion Potential
Measurement with a Rotating Cylinder Electrode in 288�C Water |
1355.pdf |
| R-356 |
Effects of Zinc Additions on the Crack
Growth Rate of Sensitized Stainless Steel and Alloys 600 and 182 in
288�C Water |
1356.pdf |
| R-357 |
On-line Measurement of Particles in
Reactor Water of BWRs |
1357.pdf |
| R-358 |
The Integrity of Inconel Alloys in
High Temperature Water Chemistry |
1358.pdf |
| R-359 |
Enriched Boron Products |
1359.pdf |
| R-360 |
Variabilities in the Calculation of
PWR Primary Coolant pH |
1360.pdf |
| R-361 |
Construction and Operation of an
In-Pile Loop for BWR Coolant Chemistry Studies |
1361.pdf |
| R-362 |
Water Chemistry During the Shut-Down
of the Boiling Water Rector Leibstadt |
1362.pdf |
| R-363 |
Solubility of Cobalt in Primary
Circuit Solutions |
1363.pdf |
| R-364 |
Statistical Analysis of Reactor Water
Data |
1364.pdf |
| R-365 |
Mixed Oxide-Alloy-Water Systems Under
LWR Conditions |
1365.pdf |
| R-366 |
Maximum Allowable Chloride Levels on
Stainless Steel Components at the Sizewell "B" PWR |
1366.pdf |
| R-367 |
Inorganic Seed Materials for the
Decontamination of PWR Aqueous Wastes |
1367.pdf |
| R-368 |
Easy Inexpensive Hydrogen Water
Chemistry Predictive Methods |
1368.pdf |
| R-369 |
Potential-pH Diagrams for Alloy-Water
Systems Under LWR Condition |
1369.pdf |
| R-370 |
In-Pile Loop Studies of Close
Reduction Technologies for PWRs and BWRs; Investigations of Material
Susceptibility to Cracking |
1370.pdf |
| R-371 |
Evaluation of Factors Affecting
Radiation Field Trends in Westinghouse-Designed Plants |
1371.pdf |
| R-372 |
The Mechanics and Kinetics of
Corrosion Product Release From Carbon Steel in Lithiated High
Temperature Water |
1372.pdf |
| R-373 |
Investigation of the Chemical and
Physical Properties of Spinel Oxides |
1373.pdf |
| R-374 |
Overview of the Impact of Stellite
Removal on Radiation Fields in KWR PWRs |
1374.pdf |
| R-375 |
Activity Transport and Corrosion
Processes in PWRs |
1375.pdf |
| R-376 |
Feasibility of On-line Monitoring of
Stress Corrosion Cracking in Rotating Components |
1376.pdf |
| R-377 |
Concept and Experience of System
Decontamination with CORD |
1377.pdf |
| R-378 |
Elomix: A Better Way of Handling the
Waste from Decontamination |
1378.pdf |
| R-379 |
BWR/5 Full-System Decontamination
Feasibility Study |
1379.pdf |
| R-380 |
Moving from Ultra-Pure BWR Water to
Plant-Tailored Water Chemistry |
1380.pdf |
| R-381 |
Effects of pH of Primary Coolant on
PWR Contamination |
1381.pdf |
| R-382 |
Behavior of PWRs in Spain Following
Changes to Modified Chemistry and Fuel Specifications |
1382.pdf |
| R-383 |
Review of Effect of Lithium on PWR
Fuel Cladding Corrosion |
1383.pdf |
| R-384 |
Shutdown Chemistry in Spanish Plants |
1384.pdf |
| R-385 |
Effect of Surface Treatment on
Radioactivity Deposition on Stainless Steel Coupons Exposed in DOEL 2 |
1385.pdf |
| R-386 |
Utility Approach to Radiation Field
Reduction By Coolant Chemistry Control |
1386.pdf |
| R-387 |
Low Picolinate LOMI - Update |
1387.pdf |
| R-388 |
Decontamination Chemistry: Current
Issues |
1388.pdf |
| R-389 |
Resin Oxidation Process Improvements |
1389.pdf |
| R-390 |
Topical Report on FSD for BWRs |
1390.pdf |
| R-391 |
SCE&G Fuel Decontamination
Qualifications Program |
1391.pdf |
| R-392 |
Pacific Nuclear Field Implementation |
1392.pdf |
| R-393 |
Utility Decontamination Experience |
1393.pdf |
| R-394 |
ABB Atom Project - ALARA 2000 |
1394.pdf |
| R-395 |
Development and Use of an In-Pile Loop
for BWR Chemistry Studies |
1395.pdf |
| R-396 |
Replacement of Pins & Rollers in
Irradiated BWR Control Blades |
1396.pdf |
| R-397 |
Cobalt Source Reduction- Control Rod
Pin & Roller Replacement |
1397.pdf |
| R-398 |
Performance of Iron-Base Hardfacing
Alloys in Gate Valves Tested Under Simulated BWR Chemistry Conditions |
1398.pdf |
| R-399 |
NOREM Wear-Resistant Alloys: An EPRI
Program Update |
1399.pdf |
| R-400 |
The Effect of Zinc on Carbon Steel and
Stainless Steel in Lithiated Coolant |
1400.pdf |
| R-401 |
Optimum Water Chemistry in Radiation
Field Buildup Control |
1401.pdf |
| R-402 |
Status Report on BWR Full System
Decontamination |
1402.pdf |
| R-403 |
Activity Pickup by Coated Coupons
Exposed in the DOEL Reactor |
1403.pdf |
| R-404 |
Primary Water Stress Corrosion
Cracking (PWSCC) Prediction Guidelines |
1404.pdf |
| R-405 |
Evaluation of Recent Experience Using
Zinc Addition to Reduce BWR Primary System Radiation Buildup |
1405.pdf |
| R-406 |
Evaluation of Fuel Rod Leakage
Mechanisms Summary Report |
1406.pdf |
| R-407 |
Development and Testing of an On-line
Iron Probe |
1407.pdf |
| R-408 |
Cost Effective Radiation Exposure
Control |
1408.pdf |
| R-409 |
Full Reactor Coolant System Chemical
Decontamination - National Demonstration |
1409.pdf |
| R-410 |
Role of Hydrogen Water Chemistry on
Dose Rates |
1410.pdf |
| R-411 |
Cobalt Source Reduction |
1411.pdf |
| R-412 |
|
1412.pdf |
| R-413 |
Radiation Field Control at Susquehanna
BWR |
1413.pdf |
| R-414 |
A Model for Corrosion Product
Transport in BWRs |
1414.pdf |
| R-415 |
Depleted Zinc Oxide Addition for BWRs |
1415.pdf |
| R-416 |
Investigation of Increased Radiation
Levels from Utilization of Hydrogen Water Chemistry in BWRs |
1416.pdf |
| R-417 |
Water Chemistry and Corrosion Effects
on Activity Buildup in BWRs Operating with Hydrogen Water Chemistry |
1417.pdf |
| R-418 |
Preparation for Field Applications of
Full System Decontamination at Indian Point 2 |
1418.pdf |
| R-419 |
Chemical Results of Full System
Decontamination at Indian Point 2 |
1419.pdf |
| R-420 |
Lessons Learned from Full Reactor
Coolant System Chemical Decontamination of a PWR |
1420.pdf |
| R-421 |
Maine Yankee Loop Stop to Loop Stop
Chemical Decontamination |
1421.pdf |
| R-422 |
DERAD - A Decommissioning Economic
Risk Advisor: Software to Analyze Decommissioning Strategices |
1422.pdf |
| R-423 |
Projected Cost Benefit for Full System
Chemical Decontamination Projects |
1423.pdf |
| R-424 |
Field Experience with Full System
Chemical Decontamination of BWR and PWR Type Reactors using the CORD
Process |
1424.pdf |
| R-425 |
Fuel-In Reactor Coolant System
Chemical Decontamination Program |
1425.pdf |
| R-426 |
Dose Rate Trends in Siemens-designed
PWRs |
1426.pdf |
| R-427 |
Dose Rate Trends in Siemens-designed
BWRs |
1427.pdf |
| R-428 |
Dose Rate Trends in
Westinghouse-designed PWRs |
1428.pdf |
| R-429 |
Improved Method for Measuring the
Effectiveness of Radiation Field Control Techniques |
1429.pdf |
| R-430 |
Effect of Various Processes on BWR
Dose Rates |
1430.pdf |
| R-431 |
Effect of VVER Water Chemistry on Dose
Rates |
1431.pdf |
| R-432 |
Experience from Severe Fuel Failures
in Ringhals: Radiological Effects and Shut-down Criteria |
1432.pdf |
| R-433 |
Development of the CAN-DEREM Plus
Reagent |
1433.pdf |
| R-434 |
Chemical Decontamination for
Decommissioning |
1434.pdf |
| R-435 |
SELCHEM: A Novel Decontamination
Process |
1435.pdf |
| R-436 |
Vanadium Analysis During LOMI
Decontamination |
1436.pdf |
| R-437 |
Recent Experience With Chemical
Decontamination |
1437.pdf |
| R-438 |
Westinghouse Recent Chemical
Decontamination Experience |
1438.pdf |
| R-439 |
Effect of Hydrogen Water Chemistry on
Chemical Decontamination |
1439.pdf |
| R-440 |
Utility Chemical Decontamination
Experience at Commonwealth Edison's Boiling Water Reactors |
1440.pdf |
| R-441 |
Assessment of Alternative
Oxidizing Reagents for Conditioning BWR and PWR Oxides |
1441.pdf |
| R-442 |
Reactor Vessel Decontamination and
Other Dose Reduction Initiatives at the Oskarshamn |
1442.pdf |
| R-443 |
Selection of the Oxidation Step in
Chemical Decontamination |
1443.pdf |
| R-444 |
Advances in Welding Iron-Base NOREM
Hardfacing Alloys |
1444.pdf |
| R-445 |
Development of Cobalt-free
Wear-Resistant Alloys for Nuclear Applications |
1445.pdf |
| R-446 |
Cobalt Balance Measurements at
Ringhals-1 BWR |
1446.pdf |
| R-447 |
Coupon Exposure Studies at DOEL-2
Using Stabilized Chromium Surface Pretreatment |
1447.pdf |
| R-448 |
Optimizing BWR Control Rod Blde
Management Strategies |
1448.pdf |
| R-449 |
PWR Primary Water Chemistry
Guidelines: Revision 3 |
1449.pdf |
| R-450 |
PWR Dose Reduction Measures at
Millstone Point-2 |
1450.pdf |
| R-451 |
Elevated pH Coolant Chemistry Control
at Millstone Point-3 |
1451.pdf |
| R-452 |
Effect on Zircaloy Clad Corrosion of
Elevated Lithium Operation at the Millstone 3 PWR |
1452.pdf |
| R-453 |
PWR Zinc Injection Experience at
Farley Unit 2 |
1453.pdf |
| R-454 |
High Pressure Water Spraying for
Boiler Head Decontamintion |
1454.pdf |
| R-455 |
Decontamination of Ontario Hydro
Pickering Unit 1 Steam Generators |
1455.pdf |
| 1-1 |
Recent Developments in Radiation Field
Control Technology |
2000.pdf |
| 1-2 |
Optimum Water Chemistry in Radiation
Field Buildup Control |
2001.pdf |
| 1-3 |
Efforts to Reduce Exposure at Japanese
PWRs: CVCS Improvement |
2002.pdf |
| 1-4 |
Efforts to Control Radiation Build-up
in Ringhals |
2003.pdf |
| 1-5 |
An Overview of Zinc Addition for BWR
Dose Rate Control |
2004.pdf |
| 1-6 |
Reduction of Radiation Exposure in
Japanese BWR Nuclear Power Plants |
2005.pdf |
| |
Panel Discussion on Recent
Recommendations on Dose Limitations |
2006.pdf |
| 3-1 |
ALARA Implementation Throughout
Project Life Cycle |
2007.pdf |
| 3-2 |
Health Physics Aspects of Advanced
Reactor Licensing Reviews |
2008.pdf |
| 3-3 |
Controlling Radiation Fields in
Siemens Designed Light Water Reactors |
2009.pdf |
| 3-4 |
ALARA Radiation Considerations for the
AP600 Reactor |
2010.pdf |
| 3-5 |
System 80+� Standard Design
Incorporates Radiation Protection Lessons Learned |
2011.pdf |
| 3-6 |
PWR Design for Low Doses in the United
Kingdom: The Present and the Future |
2012.pdf |
| 3-7 |
Implementation of ALARA at the Design
Stage of Nuclear Power Plants |
2013.pdf |
| |
Session 3 Discussion |
2014.pdf |
| |
The History of Radiation Protection |
2015.pdf |
| 4-1 |
Electricite De France's ALARA Policy |
2016.pdf |
| 4-2 |
Assessment of the Benefits and Impacts
in the U.S. Nuclear Power Industry of Hypothesized Lower Occupational
Dose Limits |
2017.pdf |
| 4-3 |
ALARA in European Nuclear
Installations |
2018.pdf |
| 4-4 |
Six Steps to a Successful
Dose-Reduction Strategy |
2019.pdf |
| 4-5 |
Progress Report on the Management of
the NEA ISOE System |
2020.pdf |
| 4-6 |
The Economics of Radiological
Protection |
2021.pdf |
| |
Session 5: Panel Discussion on
Economics vs. Excellence |
2022.pdf |
| 6-1 |
Occupational Doses and ALARA - Recent
Developments in Sweden |
2023.pdf |
| 6-2 |
ALARA and Planning of Interventions |
2024.pdf |
| 6-3 |
Peach Bottom Atomic Power Station
Recirc Pipe Dose Rates with Zinc Injection and Condenser Replacement |
2025.pdf |
| 6-4 |
ALARA Council: Sharing of Resources
and Experiences to Reduce Doses at Commonwealth Edison Facilities |
2026.pdf |
| 6-5 |
Interpretation of ALARA in the
Canadian Regulatory Framework |
2027.pdf |
| 6-6 |
Status of Zinc Injection in PWRs |
2028.pdf |
| 6-7 |
Peach Bottom Atomic Power Station Unit
3 Radiation Buildup on the Reactor Water Cleanup ( RWCU) Test Spool - An
Update |
2029.pdf |
| 6-8 |
ALARA and Work Management |
2030.pdf |
| 6-9 |
Experience with ALARA and ALARA
Procedures in a Nuclear Power Plant |
2031.pdf |
| 6-10 |
EDF Experience with "Hot Spot"
Management |
2032.pdf |
| 6-11 |
The Optimisation of Occupational
Potential Exposures |
2033.pdf |
| 6-12 |
Department of Energy ALARA
Implementation Guide |
2034.pdf |
| 7A-1 |
Primary Water Chemistry Improvement
for Radiation Exposure Reduction at Japanese PWR Plants |
2035.pdf |
| 7A-2 |
Update to Millstone 3 Elevated pH Test |
2036.pdf |
| 7A-3 |
A User Friendly Database for Use in
ALARA Job Dose Assessment |
2037.pdf |
| 7A-4 |
PWR Upper/Lower Internals Sheild |
2038.pdf |
| 7A-5 |
Report on the PWR-Radiation
Protection/ALARA Committee |
2039.pdf |
| 7B-1 |
ALARA Efforts in Nordic BWRs |
2040.pdf |
| 7B-2 |
Radiation Field Control at the Latest
BWR Plants: Design Principle, Operational Experience and Future Subjects |
2041.pdf |
| 7B-3 |
ALARA Database Value in Future Outage
Work Planning and Dose Management |
2042.pdf |
| 7B-4 |
Water Chemistry Control and
Decontamination Experience with TEPCO BWR's and the Measures Planned for
the Future |
2043.pdf |
| 7B-5 |
Report on the BWR Owners' Group
Radiation Protection/ALARA Committee |
2044.pdf |
| 8A-1 |
Use of Mock-Up Training to Reduce
Personnel Exposure at the North Anna Unit 1 Steam Generator Replacement
Project |
2045.pdf |
| 8A-2 |
Effects of Respirator Use on Worker
Performance |
2046.pdf |
| 8A-3 |
Field Experience with Remote
Monitoring |
2047.pdf |
| 8A-4 |
Westinghouse Corporate Development of
a Decision Software Program for Radiological Evaluation Decision Input (REDI) |
2048.pdf |
| 8A-5 |
Task Related Doses in Spanish
Pressurized Water Reactors Over the Period 1988-1992 |
2049.pdf |
| 8B-1 |
Scale Models: A Proven Cost-Effective
Tool for Outage Planning |
2050.pdf |
| 8B-2 |
Dose Reduction and Cost-Benefit
Analysis at Japan's Tokai No. 2 Plant |
2051.pdf |
| 8B-3 |
Radiological Controls Integration into
Design |
2052.pdf |
| 8B-4 |
PC Based Temporary Shielding
Administrative Procedure (TSAP) |
2053.pdf |
| 8B-5 |
ANI/MAELU Engineering Inspection
Criteria 8.3 ALARA |
2054.pdf |
| 8B-6 |
ALARA Development in Mexico |
2055.pdf |
| 9-1 |
Shippingport Station Decommissioning
Project ALARA Program |
2056.pdf |
| 9-2 |
Decommissioning ALARA Programs
Cintichem Decommissioning Experience |
2057.pdf |
| 9-3 |
Radiation Dose Optimisation in the
Decommissioning Plan for Loviisa NPP |
2058.pdf |
| 9-4 |
ALARA and Decommissioning - The Fort
St. Vrain Experience |
2059.pdf |
| 9-5 |
An Overview of ALARA Considerations
During Yankee Atomic's Component Removal Project |
2060.pdf |
| 9-6 |
Cold Weather Effects on Dresden Unit 1 |
2061.pdf |
| 10-1 |
Recent Developments in Chemical
Decontamination Technology |
2062.pdf |
| 10-2 |
System Decontamination as a Tool to
Control Radiation Fields |
2063.pdf |
| 10-3 |
Full Reactor Coolant System Chemical
Decontamination Qualification Programs |
2064.pdf |
| 10-4 |
National Demonstration of Full Reactor
Coolant System (RCS) Chemical Decontamination at Indian Point 2 |
2065.pdf |
| 10-5 |
Results from the Decontamination of
and the Shielding Arrangements in the Reactor Pressure Vessel in
Oskarshamn 1-1994 |
2066.pdf |
| 10-6 |
CO2 Pellet Decontamination
Technology at Westinghouse Hanford |
2067.pdf |
| 11-1 |
Mobile Robotics Application in the
Nuclear Industry |
2068.pdf |
| 11-2 |
Boiling Water Reactor Radiation
Shielded Control Rod Drive Housing Supports |
2069.pdf |
| 11-3 |
Automation of Steam Generator Services
at Public Service Electric & Gas |
2070.pdf |
| 11-4 |
Computer-Controlled Wall Servicing
Robot |
2071.pdf |
| 11-5 |
The Integrated Radiation Mapper
Assistant |
2072.pdf |
| 11-6 |
Strategy Proposed by Electricit� de
France in the Development of Automatic Tools |
2073.pdf |
| N1 |
Preventing Erosion-Corrosion at
Sizewell B |
3001.pdf |
| N2 |
How Finer Filters Can Keep Exposures
Down |
3002.pdf |
| N3 |
Enriched Boric Acid Promises Greater
Flexibility for PWRs |
3003.pdf |
| N4 |
Control Rod Drive Removal and
Installation Mechanism Saves Dose |
3004.pdf |
| N5 |
Steam Generator Pipe End Decon Saves
Approximately 100 Person-Rem |
3005.pdf |
| N6 |
More on Strippable Coatings |
3006.pdf |
| N7 |
Effect of Elevated Lithium/pH on
Inconel 600 |
3007.pdf |
| N8 |
Conductivity During Early-Life
Important in Fuel Oxidation and Failure |
3008.pdf |
| N7 |
Effect of Elevated Lithium/pH on
Inconel 600 |
3009.pdf |
| N10 |
Protective Coatings for Radiation
Control in Boiling Water Nuclear Power Reactors |
3010.pdf |
| N11 |
Designing for Maintainability |
3011.pdf |
| N12 |
Plant Inspection Experience and the
Equipment Needed |
3012.pdf |
| N13 |
Progress in Radiation Control
Technology |
3013.pdf |
| N14 |
Experience With Elevated pH at
Millstone Unit 3 |
3014.pdf |
| N15 |
Full System Decontamination Results |
3015.pdf |
| N16 |
Recent Experience with Zinc Injection |
3016.pdf |
| N17 |
Cobalt Reduction Guidelines |
3017.pdf |
| N18 |
Proceedings: 1989 EPRI Radwaste
Workshop |
3018.pdf |
| N19 |
Reduction of Critical Path Time for
BWR Recirculation System Decontaminations |
3019.pdf |
| N20 |
Proceedings: Workshop on Primary Water
Stress Corrosion Cracking |
3020.pdf |
| N21 |
Implementing Cobalt-Free Alloys in
Nuclear Plant Valves |
3021.pdf |
| N22 |
Evaluation of Iron-Based Hardfacing
Alloys |
3022.pdf |
| N23 |
Weldability Studies Update |
3023.pdf |
| N24 |
Mini-Sub in Use at Con Edison's Indian
Point 2 |
3024.pdf |
| N25 |
Lightweight Torque Wrench Improves
Bolting Maintenance |
3025.pdf |
| N26 |
Vac-Pac Technology: Safe, Clean,
Efficient Vacuum Collection |
3026.pdf |
| N27 |
Acrylic Floor Toppings Simplify
Decontamination in Nuclear Facilities |
3027.pdf |
| N28 |
Welding Arc Viewer |
3028.pdf |
| N29 |
Pipe and Tube Cutting |
3029.pdf |
| N30 |
Fuel Master Increases Capacity |
3030.pdf |
| N31 |
Looking for Steam Generator Leaks with
Helium |
3031.pdf |
| N32 |
Hall-Effect Helps |
3032.pdf |
| N33 |
Strippable Coatings Provide Leak-Tight
Integrity and Hot Particle Mitigation |
3033.pdf |
| N34 |
Effect of Electropolishing,
Preoxidation and Zinc on Radionuclide Buildup in BWR Recirculation
Piping |
3034.pdf |
| N35 |
Electropolishing Minimizes
Radioactivity Buildup |
3035.pdf |
| N36 |
Chemical Decontamination In Germany |
3036.pdf |
| N37 |
Approaching Consensus on the Optimum
pH for PWRs |
3037.pdf |
| N38 |
Collective Doses for Steam Generator
Replacements |
3038.pdf |
| N39 |
Radionuclide Buildup in BWR Reactor
Coolant Recirculation Piping |
3039.pdf |
| N40 |
Update on Full-System LWR
Decontamination |
3040.pdf |
| N41 |
Video Camera Use Reduces Cost and
Exposures |
3041.pdf |
| N42 |
Update on Primary Chemistry Guidelines
for PWRs |
3042.pdf |
| N43 |
Electropolishing Steam Generator
Channel Heads: The French Experience |
3043.pdf |
| N44 |
Current Thinking on Relative
Importance of Cobalt Reduction and Water Chemistry for PWRs |
3044.pdf |
| N45 |
The Effect of Dissolved Zinc on the
Transport of Corrosion Products in PWRs |
3045.pdf |
| N46 |
Vessel Inspection Made Easy |
3046.pdf |
| N47 |
New Alloys Resist Wear Without Costly
Cobalt |
3047.pdf |
| N48 |
New Lesson Plan Packages |
3048.pdf |
| N49 |
More on Mitsubishi's Underwater
Vehicle for Ultrasonic Vessel Inspection |
3049.pdf |
| N50 |
General Electric's New Inspection
System Gives Inside Information on BWR RPV Welds |
3050.pdf |
| N51 |
Key Tagging for Security |
3051.pdf |
| N52 |
High-Capacity Filters |
3052.pdf |
| N53 |
Ontario Hydro Proposes Canning and
Burying CANDU Reactors |
3053.pdf |
| N54 |
Strippable Coatings Help Reactor
Cavity Decon |
3054.pdf |
| N55 |
CAN-DECON Makes a Strong Comeback as
CAN-DEREM |
3055.pdf |
| N56 |
Hot Spot Reduction Program at
Braidwood |
3056.pdf |
| N57 |
Doses decreasing at Ontario Hydro |
3057.pdf |
| N58 |
Ontario Hydro: Preventative Measures
Following Overexposure |
3058.pdf |
| N59 |
Pacific Gas & Electric Upgrades
Radiation Monitoring |
3059.pdf |
| N60 |
Employee Attitudes: The Key to
Exposure Reduction at Oyster Creek |
3060.pdf |
| N61 |
EDF to Place Bulk Order for Steam
Generator Replacement |
3061.pdf |
| N62 |
French Thinking on the Comparative
Merits of Alloys 690 and 800 |
3062.pdf |
| N63 |
BWR Zinc Injection |
3063.pdf |
| N64 |
KWR Plans 54-Day Steam Generator
Replacement |
3064.pdf |
| N65 |
AEA Technology's 3D TV Equipment Shows
Performance Benefits over Conventional Television |
3065.pdf |
| N66 |
Mitsubishi's New Passive PWR |
3066.pdf |
| N67 |
Inspecting BWR In-Core Housings from
the Refueling Bridge |
3067.pdf |
| N68 |
Maintaining Dose Histories in the
United Kingdom |
3068.pdf |
| N69 |
Conclusions of the EPRI Workshop on
BWR Zinc Injection |
3069.pdf |
| N70 |
PWR Primary Water Chemistry Guidelines
- Revision 2 |
3070.pdf |
| N71 |
ICRP's New Recommendations |
3071.pdf |
| N72 |
Low Doses in ABB Atom BWRs |
3072.pdf |
| N73 |
Repairing and Replacing Steam
Generators at Soviet 1000 MWE PWRs |
3073.pdf |
| N74 |
Beznau 1 Plans Steam Generator
Replacement |
3074.pdf |
| N75 |
Aiming for Improved Steam Generator
Reliability in Japan |
3075.pdf |
| N76 |
Comparisons of Steam Generator
Replacement Techniques |
3076.pdf |
| N77 |
Quick and Easy Adjustment for Valves |
3077.pdf |
| N78 |
Smaller Dosimeter |
3078.pdf |
| N79 |
Portable Test Bench for Snubbers,
Pumps, and Steam Generators |
3079.pdf |
| N80 |
Special Cleaning Devices for
Sellafield |
3080.pdf |
| N81 |
Farewell to the Mop and Bucket |
3081.pdf |
| N82 |
NRC Decision on Level of Detail for
Advanced Reactors |
3082.pdf |
| N83 |
Replacing the Pressurizer Heater
Sleeves at Calvert Cliffs 2 |
3083.pdf |
| N84 |
Crawling Around Byron |
3084.pdf |
| N85 |
From Reaction to Proaction - Taking
the Preventative Approach |
3085.pdf |
| N86 |
Occupational Dose Reduction at NPP:
Annotated Bibliography of Selected Readings in Radiation Protection and
ALARA |
3086.pdf |
| N87 |
Combining Zinc Injection with Hydrogen
Water Chemistry |
3087.pdf |
| N88 |
Update on Zinc Injection for BWRs |
3088.pdf |
| N89 |
Latest Results from Elevated Lithium
Demo at Millstone-3 |
3089.pdf |
| N90 |
Electronic Personal Dosimeter Heralds
a Revolution in Legal Dosimetry |
3090.pdf |
| N91 |
Science Applications International's
New Small Dosimeter |
3091.pdf |
| N92 |
Techniques for Dose Reduction |
3092.pdf |
| N93 |
Consequences of Reduced Limits |
3093.pdf |
| N94 |
Getting Exposures Down at U.S. Plants |
3094.pdf |
| N95 |
The Age of the "Throwaway" Video
Camera is Here |
3095.pdf |
| N96 |
Swedish Technology Provides Inside
Knowledge of U.S. BWR Vessels |
3096.pdf |
| N97 |
Bibliography of Selected Readings on
Radiation Protection and ALARA |
3097.pdf |
| N98 |
NRC Tightens Radiation Exposure Limits |
3098.pdf |
| N99 |
Setting New Protection Standards for
Radiation |
3099.pdf |
| N100 |
Occupational Doses in ABB Atom BWRs |
3100.pdf |
| N101 |
Video Cameras at Nuclear Plants |
3101.pdf |
| N102 |
Radiation Exposures at U.S. Plants in
1990 |
3102.pdf |
| N103 |
Full System Decontamination Workshop
Planned |
3103.pdf |
| N104 |
Full System Decontamination
Qualification Programs - PWR Studies |
3104.pdf |
| N105 |
Full System Decontamination
Qualification Program - BWR Qualification Program |
3105.pdf |
| N106 |
Full System Decontamination
Qualification Programs - Comparison of Fuel In and Fuel Out |
3106.pdf |
| N107 |
Field Demonstration of NOREM
Wear-Resistant Alloys |
3107.pdf |
| N108 |
PWR Shutdown Chemistry |
3108.pdf |
| N109 |
Shutdown Radiation Fields at BWRs
Using Hydrogen Water Chemistry |
3109.pdf |
| N110 |
Robotic Maintenance Systems for
Nuclear Power Plants |
3110.pdf |
| N111 |
Expanding the Range of Activities
Performed Remotely at Nuclear Power Plants |
3111.pdf |
| N112 |
Scaffold Management - A New Era |
3112.pdf |
| N113 |
Managing of the Aging BWR Control Rod
Drive Mechanisms |
3113.pdf |
| N114 |
ALARA Reducting During CRDM Changeout
and Rebuilding |
3114.pdf |
| N115 |
CRDM Worker Training |
3115.pdf |
| N116 |
Dustless Surface Preparation and
Decontamination Systems for Concrete Floors |
3116.pdf |
| N117 |
Zinc Injection Helps Reduce Radiation
Field Buildup in BWRs |
3117.pdf |
| N118 |
Putting pH 7.2 Water Chemistry to the
Test at French PWRs |
3118.pdf |
| N119 |
EPRI-Sponsored Technology Easing CRDM
Change-Out Job at BWRs |
3119.pdf |
| N120 |
Information Exchange |
3120.pdf |
| N121 |
Collective Doses In European Light
Water Reactors |
3121.pdf |
| N122 |
Computerized Dose Tracking |
3122.pdf |
| N123 |
Advanced Technologies |
3123.pdf |
| N124 |
Dose Reduction By Outage Planning,
Strategy, and Architectural Arrangements |
3124.pdf |
| N125 |
Robotic Applications |
3125.pdf |
| N126 |
Dose Reduction During Inspection of
Germany PWRs |
3126.pdf |
| N127 |
Dose Trends in German PWRs |
3127.pdf |
| N128 |
Dose Reduction in Japan Atomic Power
Company Plants |
3128.pdf |
| N129 |
Exposure Reduction at Shimane, Unit
No. 2 |
3129.pdf |
| N130 |
Steam Generator Replacement at
Dampierre 1 |
3130.pdf |
| N131 |
Work Planning and Organization |
3131.pdf |
| N132 |
Worker Training and Responsibility |
3132.pdf |
| N133 |
Planning for Ringhals 2 Steam
Generator Replacement |
3133.pdf |
| N134 |
Swiss Experience with Zinc Injection
and Soft Shutdown |
3134.pdf |
| N135 |
CRD Services |
3135.pdf |
| N136 |
Inspection Cameras |
3136.pdf |
| N137 |
Remote Inspection |
3137.pdf |
| N138 |
Heat Stress Monitor |
3138.pdf |
| N139 |
Alarm Ratemeter |
3139.pdf |
| N140 |
Camera System |
3140.pdf |
| N141 |
UT Imaging System |
3141.pdf |
| N142 |
RPV Stud Tensioning |
3142.pdf |
| N143 |
Factors Influencing Collective
Exposure Trends |
3143.pdf |
| N144 |
The Challenge of the 1995 Radiation
Exposure Goals |
3144.pdf |
| N145 |
NRPB Opts for "Constraints" |
3145.pdf |
| N146 |
Bringing Robotic Tensioning to the
U.S. |
3146.pdf |
| N147 |
World Nuclear Industry Handbook - 1992 |
3147.pdf |
| N148 |
ALARA/ALARP: Working Well Before ICRP
60? |
3148.pdf |
| N149 |
Bar Code System |
3149.pdf |
| N150 |
Inspection Services |
3150.pdf |
| N151 |
Dosimetry Reduction |
3151.pdf |
| N152 |
Inspection Robot |
3152.pdf |
| N153 |
Inspection Robots |
3153.pdf |
| N154 |
Fluorescent Lamps |
3154.pdf |
| N155 |
Video Inspection |
3155.pdf |
| N156 |
SG Annulus Seal |
3156.pdf |
| N157 |
Standard Versus Hydrazine Water
Chemistry in VVER-440 |
3157.pdf |
| N158 |
Dose Reduction at McGuire by
Teledosimetry and Remote Communication |
3158.pdf |
| N159 |
Using Satellite Technology to Improve
Steam Generator Eddy Current Inspections |
3159.pdf |
| N160 |
An Update on the Mechanical Stress
Improvement Process |
3160.pdf |
| N161 |
Remote Operated Vehicles - A Driving
Force for Improved Outages |
3161.pdf |
| N162 |
Winning the Battle Agains IGSCC |
3162.pdf |
| N163 |
I.S.O.E. - An International
Contribution to Keep Workers' Doses ALARA |
3163.pdf |
| N164 |
ALARA - An Historical and Global
Perspective |
3164.pdf |
| N165 |
Instructions for Recording and
Reporting Occupational Exposure Data |
3165.pdf |
| N166 |
ALARA Regional Conference: Region 1 |
3166.pdf |
| N167 |
Applied Robotics Test Facility - A New
Partnership for the Mobile Robotics Community |
3167.pdf |
| N168 |
Advanced Technologies Applied to Work
Management |
3168.pdf |
| N169 |
Radiation Field Evaluations |
3169.pdf |
| N170 |
The Effect of Chemical Additives on
N-16 Carryover Under Simulated BWR Conditions |
3170.pdf |
| N171 |
Electropolishing of Replacement Steam
Generator Channel Heads at Millstone-2 PWR |
3171.pdf |
| N172 |
Update on U.S. Power Industry
Exposures |
3172.pdf |
| N173 |
Remotec's All-Terrain Robots |
3173.pdf |
| N174 |
New Remote Radiation Surveillance
System |
3174.pdf |
| N175 |
Instant Monitoring On Hand |
3175.pdf |
| N176 |
Improved Plant Designs Reduce Dose By
a Factor of 20 |
3176.pdf |
| N177 |
Dose Control at China's First Nuclear
Power Plants |
3177.pdf |
| N178 |
CANDU Large Scale Fuel Channel
Replacement Project: Individual & Collective Dose Reduction by ALARA
Integration |
3178.pdf |
| N179 |
Radiation-Field Control Manual - 1991
Revision |
3179.pdf |
| N180 |
Nuclear Power Plant Resource Book -
Vol. 2: BWR |
3180.pdf |
| N181 |
A Brief History of Robots in the
United States |
3181.pdf |
| N182 |
Trod Cleans Up At Nine Mile Point 1 |
3182.pdf |
| N183 |
More Radiation Monitoring Backfits for
the Future |
3183.pdf |
| N184 |
Designing Radiation Protection into
Sizewall B |
3184.pdf |
| N185 |
Frozen CO2 Pellets Process
for Decontamination |
3185.pdf |
| N186 |
1991 Exposure Trends |
3186.pdf |
| N187 |
Control Blade Pin and Roller
Replacement |
3187.pdf |
| N188 |
Improving Communications With Utility
Personnel |
3188.pdf |
| N189 |
Depleted Zinc Evaluation at
FitzPatrick |
3189.pdf |
| N190 |
Decontamination Update |
3190.pdf |
| N191 |
BWR Radiation Fields with Hydrogen
Water Chemistry |
3191.pdf |
| N192 |
Formation of PWR Radiation Protection/ALARA
Committee |
3192.pdf |
| N193 |
1992 Exposure Reduction Plans at Surry
Power Station |
3193.pdf |
| N194 |
Repairing the Spent Fuel Coolant Pump
at Surry: Operational Details of a Job |
3194.pdf |
| N195 |
Improved TLD Badges |
3195.pdf |
| N196 |
Pilgrim's Progress Points the Way to
Cobalt Reduction |
3196.pdf |
| N197 |
Looking for Links between BWR Hydrogen
Water Chemistry and Increased Shutdown Dose Rates |
3197.pdf |
| N198 |
New PWR Guidelines Target
Intergranular Attack and Stress Corrosion Cracking in Steam Generators |
3198.pdf |
| N199 |
Water Chemistry and Dose Reduction:
New PWRs |
3199.pdf |
| N200 |
Water Chemistry and Dose Reduction:
Millstone 3 Experience |
3200.pdf |
| N201 |
PWR Primary Coolant Chemistry and Dose
Reduction |
3201.pdf |
| N202 |
Using Divers to Inspect and Repair the
Torus Proper at Peach Bottom |
3202.pdf |
| N203 |
Scale Models - An Effective Tool for
ALARA and Constructability Planning |
3203.pdf |
| N204 |
New Developments in the Surrogate Tour
System |
3204.pdf |
| N205 |
Report on the 6th Bournemouth
Conference on Water Chemistry |
3205.pdf |
| N206 |
1992 Radiation Exposure Management
Seminar Highlights |
3206.pdf |
| N207 |
Steam Generator Strategy for Ringhals
3 and 4 |
3207.pdf |
| N208 |
Getting Ready to Replace the Steam
Generators at Doel 3 |
3208.pdf |
| N210 |
Replacing Steam Generators at
Millstone 2 |
3210.pdf |
| N211 |
Steam Generator Tube Evaluation By
Ultrasonic Testing |
3211.pdf |
| N212 |
Development of Unique In-Service
Inspection Equipment for Reactor Pressure Vessels |
3212.pdf |
| N213 |
MOOSE� Decontamination Robot Supports
Nuclear Facility's Remediation Strategy |
3213.pdf |
| N214 |
Preconditioning of PWRs |
3214.pdf |
| N215 |
Demonstration of PWR Full-System
Decontamination |
3215.pdf |
| N216 |
Demonstration of Elevated pH |
3216.pdf |
| N217 |
Current Status of PWR Primary Coolant
Chemistry in the U.S. |
3217.pdf |
| N218 |
How Hydrogen Water Chemistry Impacts
Shutdown Dose Rates in BWRs |
3218.pdf |
| N219 |
Worker Exposures Plunge at U.S. Nucear
Plants |
3219.pdf |
| N220 |
BWR and PWR Collective Radiation
Exposure |
3220.pdf |
| N221 |
Automated Reactor Vessel Stud Removal
System |
3221.pdf |
| N222 |
Hydro-Vac� Shield |
3222.pdf |
| N223 |
Chemical Decontamination of a PWR RHR
System |
3223.pdf |
| N224 |
BWR Chemistry Guidelines Revision
Committee Being Formed |
3224.pdf |
| N225 |
LOMI Decontamination of Nuclear
Reactors Reduces Exposure and Critcal Path Time |
3225.pdf |
| N226 |
GPU Cuts Critical Path Time by Using
EPRI Radwaste Desk Reference |
3226.pdf |
| N227 |
PWR Secondary Water Chemistry
Guidelines |
3227.pdf |
| N228 |
10 CFR 20's Impact on Computerized
Dose Tracking |
3228.pdf |
| N229 |
Utilities use Modified pH from Startup
to Reduce Radiation Fields |
3229.pdf |
| N230 |
Reducing Costs and Radiation Exposures
in the Nuclear Power Industry |
3230.pdf |
| N231 |
CONVOY Leads the Way on Dose Reduction |
3231.pdf |
| N232 |
Re-Revisiting the Hiroshima Dosimetry
Revision |
3232.pdf |
| N233 |
ABB-CE Applies ALARA Principles in the
Design of System 80+� PWR |
3233.pdf |
| N234 |
Use of Image Transmission and Virtual
Reality at Nuclear Plants |
3234.pdf |
| N235 |
Use of Multimedia for Nuclear Power
Plants |
3235.pdf |
| N236 |
Photogrammetry for Nuclear Power
Plants |
3236.pdf |
| N237 |
Advanced Imaging Tools for Nuclear
Power Plant Operation and Maintenance |
3237.pdf |
| N238 |
Piping System Inspection and Testing:
Managing the Massive Results, Records, and Reports |
3238.pdf |
| N239 |
Reducing Radiation Dose by Effective
ALARA Engineering |
3239.pdf |
| N242 |
Reducing Exposure at U.S. Nuclear
Plants |
3242.pdf |
| N245 |
Iron-Based Alloy Testing in BWR
Chemistries |
3245.pdf |
| N246 |
Second Meeting of the ISOE Steering
Group |
3246.pdf |
| N247 |
Some Successful Techniques for
Exposure Control |
3247.pdf |
| N248 |
Radiaton Exposure Trends |
3248.pdf |
| N249 |
Chromium Coatings to Reduce Activity
Pickup |
3249.pdf |
| N250 |
PWR Primary Chemistry Update |
3250.pdf |
| N251 |
Radiation Exposures in 1992 |
3251.pdf |
| N252 |
Robotic Vehicle |
3252.pdf |
| N253 |
Radiation Shielding |
3253.pdf |
| N254 |
Managing CRDM Nozzle Cracking |
3254.pdf |
| N255 |
Performance Monitoring Tool |
3255.pdf |
| N256 |
UK Goes for 20 MsV Limit |
3256.pdf |
| N257 |
U.S. Nuclear Power Plant Performance
Improves Again in 1992 |
3257.pdf |
| N258 |
Dose Data From BWR Owner's Group Rp/A
Committee |
3258.pdf |
| N259 |
Nuclear Plant Discharges Too Low to
Detect |
3259.pdf |
| N260 |
Present and Future Safety Issues for
�lectricit� de France (EdF) |
3260.pdf |
| N261 |
Listening to Reactor Pressure at the
Boundaries for the Sounds of Cracks and Leaks |
3261.pdf |
| N262 |
The Safety of French Pressurized Water
Reactors: A Regulator's Perspective |
3262.pdf |
| N263 |
Options for Leak Detection |
3263.pdf |
| N264 |
Good Experience From Operation of
Replacement Steam Generators |
3264.pdf |
| N265 |
Remote Handling Equipment Aids Bruce
Nuclear Power Station |
3265.pdf |
| N266 |
EPRI's Low Level Waste, Chemistry and
Radiation Control Program |
3266.pdf |
| N267 |
European Utility Requirements for the
Next Generation of Nuclear Plant |
3267.pdf |
| N268 |
New Steam Generators for Doel 3 |
3268.pdf |
| N269 |
Worker Protection during Contaminated
Concrete and Steel Remediation |
3269.pdf |
| N270 |
More Circumferential Cracking
Indications Found in Ringhals 2 Upper Head |
3270.pdf |
| N271 |
A Record-Breaking SG Replacement |
3271.pdf |
| N272 |
Neutron Detectors |
3272.pdf |
| N273 |
An Electronic Personal Dosimeter
System |
3273.pdf |
| N274 |
Scaffolding Management for Waste and
Dose Minimization |
3274.pdf |
| N275 |
Reactor Vessel Stuck Stud Removal and
Stud Hole Repair |
3275.pdf |
| N276 |
Refurbising Rather than Replacing
Reactor Coolant Pump Motors |
3276.pdf |
| N277 |
Service Water Restoration at North
Anna |
3277.pdf |
| N278 |
Planning SG Replacement Pays Off for
North Anna |
3278.pdf |
| N279 |
Lasers Make Light Work of Sleeving |
3279.pdf |
| N280 |
Japanese Wrestle with Tube Problems |
3280.pdf |
| N281 |
Paving the Way for Full System
Decontamination with the Fuel In |
3281.pdf |
| N282 |
Developing the Reactor Operating
Procedures for Full-System Decontamination |
3282.pdf |
| N283 |
Laying the Foundations for the Field
Implementation of Full System Decontamination |
3283.pdf |
| N284 |
Preparing for Full System
Decontamination at Indian Point 2: Utility Perspective |
3284.pdf |
| N285 |
The Road to Full RCS Decontamination |
3285.pdf |
| N286 |
Chemical Decontamination Workshop |
3286.pdf |
| N287 |
Surrogate Video Tour |
3287.pdf |
| N288 |
Temporary Shielding for RHR Piping |
3288.pdf |
| N289 |
Browns Ferry Nuclear Plant Unit 2
Cycle 6 Chemical Decontamination Proven Success |
3289.pdf |
| N290 |
Automating Pump Nozzle Inspection |
3290.pdf |
| N291 |
Automating Inspection of Vessel
Penetrations in French PWRs |
3291.pdf |
| N292 |
Japan in Nearly Reaching the Limits of
Automated Inspection |
3292.pdf |
| N293 |
Combining AL and NDE to Aid Pipework
Repair and Inspection Decision |
3293.pdf |
| N294 |
Replacement of Separator Shroud Bolts |
3294.pdf |
| N295 |
A Brief History of Robots in the US |
3295.pdf |
| N296 |
Robotics, Video, and Advanced
Technologies for ALARA |
3296.pdf |
| N297 |
U/MRUG: Utility/Manufacturers Robotics
Users Group |
3297.pdf |
| N298 |
Robotics and the Power Plant of the
Future |
3298.pdf |
| N299 |
The Economics of Robots in Nuclear
Power Plants |
3299.pdf |
| N300 |
Robotic Arm Cleaning |
3300.pdf |
| N301 |
A Remotely Operated Excavator |
3301.pdf |
| N302 |
Bringing Robotic Tensioning to the US |
3302.pdf |
| N303 |
Japan's ARTRA Robot Moves Forward |
3303.pdf |
| N304 |
ROSA III: The Westinghouse Workhorse |
3304.pdf |
| N305 |
Automating Fuel Handling Systems |
3305.pdf |
| N306 |
TROD Cleans Up at Nine Mile Point 1 |
3306.pdf |
| N307 |
Installing Nozzle Dams 100% Remotely |
3307.pdf |
| N308 |
Making Tracks to Clean-Up After
Accidents |
3308.pdf |
| N309 |
CECIL Lances Bruce's Boilers |
3309.pdf |
| N310 |
TELEMAN, Europe's Tele-Robotic Program
to End |
3310.pdf |
| N311 |
Emphasis on Contamination Control
Brings MOOSE to FMC Superfund Site |
3311.pdf |
| N312 |
Robots in PSE&G's Nuclear Plants
Experience and Future Projections |
3312.pdf |
| N313 |
Water-Soluble Glues Qualified for BWRs |
3313.pdf |
| N314 |
Small-Scale Models Equal Large-Scale
Savings |
3314.pdf |
| N315 |
New Technical Group for
Decommissioning, Decontaminating, and Reutilization Formed by the
American Nuclear Society |
3315.pdf |
| N316 |
Dustless Decontamination Well
Established at US DOE Sites |
3316.pdf |
| N317 |
Video System |
3317.pdf |
| N318 |
Hanford, Where Should We Begin? |
3318.pdf |
| N319 |
Developing Decon |
3319.pdf |
| N320 |
Instrument Port Column Assembly (IPCA)
Upgrade |
3320.pdf |
| N321 |
Getting Longer Life from Roller Nut
Control Rod Drives |
3321.pdf |
| N322 |
US Industry Lauds Rise in Performance |
3322.pdf |
| N323 |
Symposium on Radioactive and Mixed
Waste - Risk as a Basis for Waste Classification |
3323.pdf |
| N324 |
Power Up at Bruce |
3324.pdf |
| N325 |
Radiation Worker Study Links Leukemia
with Exposure |
3325.pdf |
| N326 |
Through-Wall Upper Vessel Head Cracks
at Jose Cabrera |
3326.pdf |
| N327 |
Temporary Repair to Ringhals Head |
3327.pdf |
| N328 |
Doubts Persist on Decommissioning |
3328.pdf |
| N329 |
Early Decommissioning Cheaper, NRC
Says |
3329.pdf |
| N330 |
Old Times for New: The Cheaper
Solution to Valve Problems |
3330.pdf |
| N331 |
Comparing National Approaches to NDE |
3331.pdf |
| N332 |
Tube Problems: Worldwide Statistics
Reviewed |
3332.pdf |
| N333 |
SG Replacement Problems Anticipated
and Avoided with 3D CAD |
3333.pdf |
| N334 |
Some Good ALARA Practices at Big Rock
Point (Part I) |
3334.pdf |
| N359 |
Some Good ALARA Practices at Big Rock
Point (Part II, Continued) |
3335.pdf |
| N361 |
Three-Year Capacity Factors Rose Again |
3337.pdf |
| N362 |
The Brave New World of Micro Robotics
is Here |
3338.pdf |
| N363 |
Study Shows Need for More Nuclear
Power |
3339.pdf |
| N364 |
Pickering Leak Contained |
3340.pdf |
| N365 |
Nuclear Industry in Action |
3341.pdf |
| N366 |
Radiation Protection: Utilizing A
Digital Camera |
3342.pdf |
| N367 |
PWRs to Assess Steam Generator
Problems for NRC |
3343.pdf |
| N368 |
Taking in the Sites |
3344.pdf |
| N369 |
Utility Embarks on Massive Sleeving
Job |
3345.pdf |
| N370 |
NRC Issues Favorable Inspection Report |
3346.pdf |
| N371 |
Nuclear Plant Reliability Data System
(NPRDS): A Tool for Success |
3347.pdf |
| N372 |
Bringing the Industry to Dresden |
3348.pdf |
| N373 |
Full-System Decontamination of Indian
Pont 2 |
3349.pdf |
| N374 |
Decommissioning Plan for Big Rock
Point |
3350.pdf |
| N375 |
Advisers Ok ORC's Steam Generator
Repair Criteria |
3351.pdf |
| N376 |
Refueling, Power Uprate Outage
Extended a Week at WNP-2 |
3352.pdf |
| N377 |
Virginia Power Completes Outage Under
Budget |
3353.pdf |
| N378 |
More Vessel Head Repairs Approved for
Jose Cabrera |
3354.pdf |
| N379 |
Kewaunee is Back but with Reduced
Power |
3355.pdf |
| N380 |
Consolidated Edision (ConEd)
Decontaminated Reactorcoolant Water |
3356.pdf |
| N381 |
Possible Westinghouse Tube Plug Cracks
Could Lead to Replacement Order |
3357.pdf |
| N382 |
NU Prepares for Restart After Problems |
3358.pdf |
| N383 |
SG Modifications May Provide Life
Extension |
3359.pdf |
| N384 |
A Plugged SG Tube Burst at Haddam Neck |
3360.pdf |
| N385 |
Zorita Restart has been Approved |
3361.pdf |
| N386 |
SONGS Favours Proven Technology |
3362.pdf |
| N387 |
Cameras Offer a Clearer Picture to
ALARA Group |
3363.pdf |
| N388 |
HP Video, Audio System Saves Dose
During Outage |
3364.pdf |
| N389 |
A Primary Containment Vessel
Inspection Robot at Tokyo Electric |
3365.pdf |
| N391 |
How to Choose a Manipulator? |
3366.pdf |
| N392 |
Automating Steam Generator Maintenance
at Bruce A |
3367.pdf |
| N393 |
Using Robots for Decommissioning |
3368.pdf |
| N394 |
Robotic Inspection of Reactor Pressure
Vessel by URSULA |
3369.pdf |
| N395 |
Decontamination of Large Metal Objects |
3370.pdf |
| N404 |
Comprehensive Low-Cost Reliability
Centered Maintenance |
3379.pdf |
| N405 |
Chromium Coatings to Reduce Radiation
Buildup |
3380.pdf |
| N406 |
NOREM Application Guidelines |
3381.pdf |
| N407 |
TVA Saves Critical Outage Time for
Examination of RPV and Internals Lifting Device |
3382.pdf |
| N409 |
Effect of Nuclear Power Plant
Decommissioning Costs on Plant Life Cycle Decision |
3384.pdf |
| N3409 |
LWR Occupational Dose Data for 1995 |
3409.pdf |
| N3410 |
Proceedings: 1996 ASME/EPRI Radwaste
Workshop |
3410.pdf |
| N3411 |
Interim On-Site Storage of Low Level
Waste: Guidelines for Extended Storage |
3411.pdf |
| N3412 |
Effect of Injection of Depleted Zinc
on Radiation Fields of Lasalle 1 BWR |
3412.pdf |
| N3413 |
Controlling Radiation Fields at
Monticello BWR When Using Hydrogen Water Chemistry |
3413.pdf |
| N3414 |
Calvert Cliffs: Using PSAs to Assess
On-Line Maintenance Risks |
3414.pdf |
| N3415 |
South Texas: PSA Techniques Used in
Day-to-Day Activities |
3415.pdf |
| N3416 |
Bill Lee Leaves a Legacy of Leadership
to Nuclear Professionals Worldwide |
3416.pdf |
| N3417 |
The Nuclear Maintenance |
3417.pdf |
| N3418 |
Evaluation of Zinc Addition to Primary
Coolant of Farley-2 PWR |
3418.pdf |
| N3419 |
Getting the Dose Problem Under Control
in Sweden |
3419.pdf |
| N3420 |
The Potential of Decontamination |
3420.pdf |
| N3421 |
ALARA Programming for Swedish Plants |
3421.pdf |
| N3422 |
Japan Plans All-Purpose Electronic
Dosimetry System |
3422.pdf |
| N3423 |
Addressing the Problems of Stress
Corrosion Cracking in PWR Control Rod Drive Mechanism Penetrations |
3423.pdf |
| N3424 |
Evaluation of the Key Factors Analysis
Technique as an ALARA Tool |
3424.pdf |
| N3425 |
Evaluation of PWR Radiation Fields:
1991-1996 |
3425.pdf |
| N3426 |
Cycle Chemistry Improvement Program |
3426.pdf |
| N3427 |
Proceedings: EPRI/DOE International
Conference on Managing Hazardous and Particulate Air Pollutants |
3427.pdf |
| N3428 |
Evaluation of Alternative Filter
Elements for Condensate Polishing Applications at Catawba Nuclear
Station |
3428.pdf |
| N3429 |
Users Manual, Wastecost: Wet Module,
Version 1.0 |
3429.pdf |
| N3430 |
French Optimizing Outage Time, Doses
in Steam Generator Replacements |
3430.pdf |
| N3431 |
French Ministries Order New Study of
Leukemia Cases Near La Hague |
3431.pdf |
| N3432 |
Dose in 90 Days Before Conception
Meant More Boys Born at Sellafield |
3432.pdf |
| N3433 |
France May Ban Temporary Workers From
Radiation Work at EDF Plants |
3433.pdf |
| N3434 |
Instruction Concerning Risks from
Occupational Radiation Exposure |
3434.pdf |
| N3435 |
NRC Taking a New Look at Safety Issues |
3435.pdf |
| N3436 |
Notes on 1997 International ALARA
Symposium, Orlando, Florida, March 16-20, 1997 |
3436.pdf |
| N3437 |
Taking the Chemistry Out of
Decontamination |
3437.pdf |
| N3438 |
Steam Generator Feedring Modification
ALARA |
3438.pdf |
| N3439 |
Steam Generator Replacement Ringhals
3, 195 |
3439.pdf |
| N3440 |
A Radiation Protection Approach to the
Implementation of Work Management |
3440.pdf |
| N3441 |
Computer Based Training - "Radiation
Protection" - An ALARA Training Tool |
3441.pdf |
| N3442 |
ALARA Considerations for PWR Reactor
Vessel Annealing |
3442.pdf |
| N3443 |
Work Management in the Nuclear Pwer
Industry |
3443.pdf |
| N3444 |
Objective Control in Dose Management |
3444.pdf |
| N3445 |
Becoming a World Class ALARA Performer
with EPRI Technology |
3445.pdf |
| N3446 |
Achieving Short Outages and Low Doses |
3446.pdf |
| N3447 |
ALARA Program in the New Generation of
Advanced BWRs |
3447.pdf |
| N3448 |
Management for the Optimization of
Radiation Exposre in Spanish Nuclear Power Plants |
3448.pdf |
| N3449 |
Maintaining Public Dose ALARA After
Decommissioning |
3449.pdf |
| N3450 |
Effect of Hydrogen Water Chemistry on
Chemical Decontamination |
3450.pdf |
| N3451 |
A Radiation Protection Approach to the
Implementation of Work Management |
3451.pdf |
| N3452 |
A New Water Chemistry Control Method
for Radiation Reduction of BWR |
3452.pdf |
| N3453 |
The S.R.T. Project: Mobile Robots for
Inspection in Nuclear Power Plants |
3453.pdf |
| N3454 |
The Management of Radiation Protection
in EDF Nuclear Power Plants |
3454.pdf |
| N3455 |
Electricite de France ALARA Project |
3455.pdf |
| N3456 |
Achieving Short Outages and Low Dose |
3456.pdf |
| N3457 |
Integrated Electrometer Dosimeter and
Dose Records Systems |
3457.pdf |
| N3458 |
Automated Health Physics Monitoring |
3458.pdf |
| N3459 |
Remote Area Monitoring Industry
Overview |
3459.pdf |
| N3460 |
PWR Shutdown Chemistry Control During
Short Duration Outages |
3460.pdf |
| N3461 |
Property Damage Risk Assessment
Scooping Study |
3461.pdf |
| N3462 |
PISCES: Power Plant Chemical
Assessment Model - Version 2.0 |
3462.pdf |
| N3463 |
Analysis of Steam Generator Tubing
from Oconee Unit 1 Nuclear Station |
3463.pdf |
| N3464 |
Waste Acounting |
3464.pdf |
| N3465 |
Decontamination of BWR Systems Using
NP/LOMI Preoxidation Steps |
3465.pdf |
| N3466 |
ANS/UMRUG Meeting on Robotics |
3466.pdf |
| N3467 |
Steam Generator Inspection and
Cleaning: UBIB & UBHC |
3467.pdf |
| N3468 |
Networking Protocol |
3468.pdf |
| 3469 |
Conference on Interaction of
Non-Iron-Based Materials with Water and Steam |
3469.pdf |
| 3470 |
Recommendations for an Effective Flow
Accelerated Corrosion Program |
3470.pdf |
| 3471 |
PWR Secondary Water Chemistry
Guidelines Revision 4 |
3471.pdf |
| 3472 |
State-of-the-Art Weld Repair
Technology for High Temperature and Pressure Parts |
3472.pdf |
| 3473 |
Proceedings: Specialist Meeting on
Environment Degradation of Alloy 600 |
3473.pdf |
| 3474 |
WASTECOST Handbook |
3474.pdf |
| 3475 |
Full System Decontamination of the
Indian Point 2 PWR |
3475.pdf |
| 3476 |
Chemical Decontamination with
Preoxidation Steps: BWR Systems at Plant Hatch |
3476.pdf |
| 3477 |
Experience with Depleted Zinc Oxide
Injection in BWRs |
3477.pdf |
| 3478 |
Study on High Temperature Chemical
Cleaning Tests and Appliances |
3478.pdf |
| 3479 |
Steam Generator Tube Fatigue
Evaluation |
3479.pdf |
| 3480 |
Condensate Polishing Guidelines |
3480.pdf |
| 3481 |
Permanent Lead Shielding for Nuclear
Safety Piping Systems |
3481.pdf |
| 3482 |
Analysis of Steam Generator Tubing
from Crystal River, Unit 3 |
3482.pdf |
| 3483 |
Operating Limits for Silica, Calcium,
Aluminum, and Magnesium in PWRs |
3483.pdf |
| 3484 |
Plant-Specific Optimization of LWR
Water Chemistry |
3484.pdf |
| 3485 |
PWR Fuel-In Full Reactor Coolant
System Decontamination Qualification |
3485.pdf |
| 3486 |
Impact of PWR Primary Chemistry on
Corrosion Product Deposition on Fuel Cladding Surfaces |
3486.pdf |
| 3491 |
Changing Times for Radiological
Protection Managers |
3491.pdf |
| 3492 |
ALARA Progress in the European Union
and Russia |
3492.pdf |
| 3493 |
Putting Radiation Protection
Information on the Internet |
3493.pdf |
| 3494 |
Maine Yankee Steam Generator Tube
Modification from a Radiological Perspective |
3494.pdf |
| 3495 |
Collective Dose Reduction at
Washington Nuclear Project-2 |
3495.pdf |
| 3496 |
How to Reduce Dose and Costs: Add Lead
to Your Metallic Insulation |
3496.pdf |
| |
|
4000.pdf |
| 1 |
Remote Handling Machines for BWR
Control Rod Drives |
6001.pdf |
| 2 |
Processes and Practices Related to
Occupational Dose: Automatic or Semi-Automatic Ultrasonic Inspection
Systems |
6002.pdf |
| 3 |
Cattle Chute Shielding for BWRs |
6003.pdf |
| 4 |
Cavity Wall and Other Special
Decontamination Machines |
6004.pdf |
| 5 |
Chemical Decontamination of Primary
Systems |
6005.pdf |
| 6 |
Chloride Concentration Control |
6006.pdf |
| 7 |
Clean-Up Procedure for Valve Seat
Grinding |
6007.pdf |
| 8 |
Cobalt QA Procedures on Inconel Fuel
and Grids (PWRs) and on Fuel, Pins, and Control Blades (BWRs) |
6008.pdf |
| 9 |
Condensate Prefilters |
6009.pdf |
| 11 |
Conoseal Modification for Incore
Thermocouple Penetration (PWRs) |
6011.pdf |
| 13 |
Electropolishing of Steam Generator
Channel Heads |
6013.pdf |
| 14 |
Electropolishing Refueling Tools;
Lifting Rigs; and New Piping |
6014.pdf |
| 15 |
Eliminate Antimony in Main Coolant
Pump Bearings (PWRs) |
6015.pdf |
| 16 |
Eliminate Reactor Temperature Detector
Bypass Manifold (PWRs) |
6016.pdf |
| 17 |
Iron Control (BWRs) |
6017.pdf |
| 18 |
Forward Pumped Heater Drains (BWRs) |
6018.pdf |
| 19 |
Fuel Cycle Length |
6019.pdf |
| 20 |
Fuel Sipping |
6020.pdf |
| 21 |
Fuel Rod Cleaning |
6021.pdf |
| 22 |
Hight Temperature Electromagnetic
Filtration on the Primary Circuit of LWR Plants |
6022.pdf |
| 23 |
Hot Spot Reduction |
6023.pdf |
| 24 |
Hydrogen Water Chemistry for BWRs |
6024.pdf |
| 26 |
Magnetic Filters |
6026.pdf |
| 27 |
MSIV Automatic Lapping and Handling
Equipment (BWR) |
6027.pdf |
| 27.1 |
Main Steam Isolation Valve Maintenance |
6028.pdf |
| 29 |
Minimize and Control Crud Burst During
Shutdown |
6029.pdf |
| 31 |
Multi-Stud Tensioners for RV Head |
6031.pdf |
| 32 |
Oxygen Control in Feedwater and
Reactor Water |
6032.pdf |
| 33 |
Passivation of Piping in LWRs |
6033.pdf |
| 36 |
Permanent Work Platforms |
6036.pdf |
| 37 |
Role of pH Control in Controlling PWR
Radiation-Field Buildup |
6037.pdf |
| 39 |
Quick-Disconnect Insulation |
6039.pdf |
| 40 |
Quick-Opening Hatch for PWR Fuel
Transfer Tube |
6040.pdf |
| 41 |
Reactor Vessel Head Shield |
6041.pdf |
| 42 |
Utilization of Enriched Boric Acid in
PWRs |
6042.pdf |
| 43 |
Refueling Machine |
6043.pdf |
| 44 |
Refueling Equipment Modifications |
6044.pdf |
| 45 |
Remote Tooling; Robotics; and Remote
Surveillance |
6045.pdf |
| 46 |
Replacement of Worn Valve or Internal
Parts with Low-Cobalt or Cobalt-Free Alloys |
6046.pdf |
| 47 |
"Wet Motor" Sealless Pumps for Water
Clean Up Systems in BWRs |
6047.pdf |
| 47.1 |
Seal-less Pumps for Reactor Water
Clean-Up (RWCU) |
6048.pdf |
| 48 |
Semi-Automatic BWR CRD Overhauling and
Inspection Device |
6049.pdf |
| 49 |
BWR Turbine Shield Wall |
6050.pdf |
| 50 |
Shutdown When Fuel Leaks |
6051.pdf |
| 51 |
Snubber and Pipe-Whip Restraint
Reduction |
6052.pdf |
| 52 |
Special Sheilds |
6053.pdf |
| 53 |
Specification of Cobalt in Steam
Generators (PWRs) |
6054.pdf |
| 56 |
Thread Cleaner for Studs of Reactor
Vessel Head |
6056.pdf |
| 57 |
Use of Ultrafine Filters to Reduce
Radiation Levels; Hot Spots and Hot Particle Problems |
6057.pdf |
| 58 |
Valve and Valve Packing Improvement
Program |
6058.pdf |
| 59 |
Viewing Windows |
6059.pdf |
| 60 |
Wide-Range Neutron Monitoring Systems
(BWRs) |
6060.pdf |
| 61 |
Zinc in Reactor Water or Zinc
Injection (BWRs) |
6061.pdf |
| 62 |
Iron/Nickel Control |
6062.pdf |
| 63 |
Prefilming and Preconditioning of
Primary Piping |
6063.pdf |
| 64 |
Improved Filters for Primary Coolant |
6064.pdf |
| 66 |
Snubber Reduction |
6066.pdf |
| 70 |
Cobalt Reduction with Cobalt-Free
Hardfacing Alloys in BWRs |
6070.pdf |
| 71 |
Condenser Leak Detection |
6071.pdf |
| 72 |
Main Steam Line Plugs |
6072.pdf |
| 73 |
ISI Exposure Reduction Methods |
6073.pdf |
| 74 |
Semi-Automatic CRD Disassembly and
Cleaning System |
6074.pdf |
| 76 |
Utility Services |
6076.pdf |
| 77 |
BWR-Temporary Radiation Shields for
Control Rod Drive Flanges of BWRs |
6077.pdf |
| 79 |
Main Steam Isolation Valve Leakage
Improvements |
6079.pdf |
| 1001 |
ALARA Campaign |
6501.pdf |
| 1002 |
ALARA Committee |
6502.pdf |
| 1003 |
ALARA Suggestion Program |
6503.pdf |
| 1005 |
Engineering Design and Review for
ALARA |
6505.pdf |
| 1006 |
Management Commitment to ALARA |
6506.pdf |
| 1007 |
ALARA Job Reviews and Planning |
6507.pdf |
| 1008 |
Maintenance Cleanliness Programs |
6508.pdf |
| 1009 |
Mockup Training and Dry Runs |
6509.pdf |
| 1010 |
Dose Reduction Processes Evaluation
and Prioritization Plan |
6510.pdf |
| 1012 |
ALARA Training |
6512.pdf |
| 1013 |
Video-Taping Repetitive High-Dose Jobs |
6513.pdf |
| 1014 |
Worker Training for Self-Monitoring |
6514.pdf |
| 1015 |
Photographic Records of Plant Areas
and Components |
6515.pdf |
| 1016 |
Radiation Maps of Radiation Areas |
6516.pdf |
| 1017 |
Value of Person-REM in Cost-Benefit
Evaluations |
6517.pdf |
| 1018 |
Health Physics Coverage by Video for
Repetitive High-Dose Jobs |
6518.pdf |
| 1020 |
Special Working Compartments with HEPA
Filters |
6520.pdf |
| 1021 |
Cost-Benefit Analysis and Payback
Periods |
6521.pdf |
| 1022 |
Third Party Review of Dose Reduction
Practices |
6522.pdf |
| |
1 Regulatory Limits |
7000.pdf |
| |
Table 1.1 Comparison of occupational
air concentration limits |
7001.pdf |
| |
2 Administrative Limits |
7002.pdf |
| |
3 ICRP and NCRP Recommendations on
Dose Limits |
7003.pdf |
| |
4 Removable Contamination Limits for
Packing and Transportation |
7004.pdf |
| |
5 Radiological Hazards |
7005.pdf |
| |
6 Probable Effects of Acute Whole Body
Doses |
7006.pdf |
| |
7 Control of External Radiation
Exposure |
7007.pdf |
| |
7.1 Absorption of Beta Radiation |
7008.pdf |
| |
8 Internal Radiation Hazards |
7009.pdf |
| |
9 Internal Dose |
7010.pdf |
| |
Table 9.2 Air sampling recommendations
based on estimated intakes and airborne concentrations |
7011.pdf |
| |
10 Radioiodine Data |
7012.pdf |
| |
11 Guidelines for Protective Apparel |
7013.pdf |
| |
Table 11.1 Utility guidelines for the
use of protective apparel |
7014.pdf |
| |
12 Guidelines for Radiation Monitoring |
7015.pdf |
| |
14 Suggestions for the Control of
Contamination |
7017.pdf |
| |
Table 14.1 Personnel decontamination |
7018.pdf |
| |
Table 14.2 Area and material
decontamination |
7019.pdf |
| |
15 Guidelines for Heat Stress Control |
7020.pdf |
| |
Table 15.2 Stay times without cooling
or other controls |
7021.pdf |
| |
15.1 Determination of Action Time |
7022.pdf |
| |
16 Shielding |
7023.pdf |
| |
17 General Suggestions on How to
Perform Surveys |
7024.pdf |
| |
How to Perform Gamma Surveys |
7025.pdf |
| |
How to Measure Airborne Particulate
and Radioiodine Activity |
7026.pdf |
| |
How to do Direct Beta-Gamma
Contamination Surveys |
7027.pdf |
| |
How to do Indirect Beta-Gamma
Contamination Surveys |
7028.pdf |
| |
How to Perform Beta Surveys Using the
Low-Range Beta Meter |
7029.pdf |
| |
18 Using Multiple Badges for Dosimetry |
7030.pdf |
| |
19 Hot Particles |
7031.pdf |
| |
20 Hot Spots |
7032.pdf |
| |
21 Conversion from Units of
Radioactivity |
7033.pdf |
| |
22 Activity Data |
7034.pdf |
| |
23 Useful Formulae |
7035.pdf |
| |
24 Work Planning |
7036.pdf |
| |
Safety Checklist |
7037.pdf |
| |
25 Apparent Exposure Reduction
Potential (ARP) |
7038.pdf |
| |
26 List of High-Dose Worker Groups |
7039.pdf |
| |
Table 26.1 Sample data sheet for
in-service inspectors and quality assurance technicians |
7040.pdf |
| |
Table 26.2 Sample data sheet for
radwaste handlers and decontamination workers |
7041.pdf |
| |
Table 26.3 High-dose group data sheet |
7043.pdf |
| |
27 High-Dose Jobs in Nuclear Power
Plants |
7044.pdf |
| |
27.2 High-Dose Jobs in BWRs |
7045.pdf |
| |
28 Dose Reduction |
7046.pdf |
| |
28.2 PWR Repetitive High-Dose Job -
Dose-Reduction Data Sheets |
7047.pdf |
| |
29 Radiation Field Control Manual -
1991 Revision |
7048.pdf |
| |
30 Basic Questions to Evaluate Your
ALARA Program |
7049.pdf |
| |
31 Man-Rem Dollar Values in Use at
U.S. Nuclear Power Plants |
7050.pdf |
| |
32 List of Most Effective
Modifications |
7051.pdf |
| |
32.2 Cost-Effective Modifications |
7052.pdf |
| |
33 Worksheets for Cost/Benefit
Analysis |
7053.pdf |
| |
34 Column Charts of What Utilities
Consider Most Effective Processes |
7055.pdf |
| |
35 ALARA Center Services |
7056.pdf |
| |
35.2 ACEFAX - Obtaining Information
through fax |
7057.pdf |
| |
35.3 ACEFAX Accessing Procedure and
ALARA Center Phone Number Guide |
7058.pdf |
| |
35.5 ALARA Center Publications |
7060.pdf |
| |
35.6 ALARA Center Information Request
Form |
7061.pdf |
| |
36 Elements of an ALARA Program |
7062.pdf |
| |
37 Directory of Nuclear Power Plants |
7063.pdf |
| |
38.1 ALARA Review of Facilities and
Equipment Design and Modification ( Tennessee Valley Authority) |
7064.pdf |
| |
38.2 ALARA Program Pre-Job Checklist
(Tennessee Valley Authority) |
7065.pdf |
| |
38.3 Sample Preliminary Radiological
Impact/Evaluation Checklist (Tennessee Valley Authority) |
7066.pdf |
| |
ALARA Checklist |
7067.pdf |
| |
39.1 ALARA Program: Pre-Job
Considerations (Ontario Hydro) |
7077.pdf |
| |
39.2 Example of a Radiation Exposure
System: Planning Verification Report (Tennessee Valley Authority) |
7078.pdf |
| C |
Characteristics of Air Sampling |
7083.pdf |
| D |
Abbreviations Used at Nuclear Power
Plants |
7084.pdf |
| D1 |
Vitrification of Low-Level Radioactive
Waste |
8001.pdf |
| D2 |
Spent Resin Disposition - Available
Alternatives and Selection Analysis |
8002.pdf |
| D3 |
Westinghouse Unveils Wes Strip |
8003.pdf |
| D4 |
Zero Plastics and the Radiological
Protected Area Low Level Waste Lockout Program |
8004.pdf |
| D5 |
Shoreham Decommissioning: Project
Summary and Lessons Learned |
8005.pdf |
| D6 |
Cleaning Up With Carbon Dioxide |
8006.pdf |
| D7 |
Sludge Management Systems |
8007.pdf |
| D8 |
Assessment of a Low-Level Waste
Outside Storage Pad Design Method |
8008.pdf |
| D9 |
Environmental Performance Measurement |
8009.pdf |
| D10 |
Radwaste Desk References |
8010.pdf |
| D11 |
Hanford Tank-Waste Strategy Proposed |
8011.pdf |
| D12 |
Grand Junction Produces Environmental
Cleanup Directory |
8012.pdf |
| D13 |
Engineering Change Process Reduces
Cost and Improves Results |
8013.pdf |
| D14 |
Sludge Collection and Filtration
System |
8014.pdf |
| D15 |
Using Pollution Prevention to Reduce
Hazardous Waste Genertaion and Handling/Disposal Costs |
8015.pdf |
| D16 |
EM Group Explodes Privatization Issues |
8016.pdf |
| D18 |
Decontamination by Pentak |
8018.pdf |
| D19 |
Management Contract RFP Elicits Three
Proposals |
8019.pdf |
| D20 |
EPA Issues Criteria for Standard
Compliance |
8020.pdf |
| D21 |
Proceedings: Vitrification of
Low-Level Waste - The Process and Potential |
8021.pdf |
| D22 |
Transatlantic Partnership |
8022.pdf |
| D23 |
Decommissioning Planning When There is
No Place to Put the Waste (Part I) |
8023.pdf |
| D24 |
Decommissioning Planning When There's
No Place to Put Waste (Part II) |
8024.pdf |
|
D25 |
Spent Fuel Canister |
8025.pdf |
|
D26 |
Gamma Scanner |
8026.pdf |
|
D27 |
Multichannel Analyzer |
8027.pdf |
|
D28 |
Alpha Analyst |
8028.pdf |
|
D29 |
DOE Issues Requests for Proposal for
Tank Waste Solidification |
8029.pdf |
|
D30 |
DOE Unveils Low-Level Waste Container
Policy |
8030.pdf |
|
D31 |
Mixed-Waste Project at Idaho National
Engineering Laboratory |
8031.pdf |
|
D32 |
Teaming and Innovation are Hanford
Recipe for Success |
8032.pdf |
|
D33 |
Targeting the "Worst of the Worst"
Spent Nuclear Fuel |
8033.pdf |
|
D34 |
A Gem of an Idea for Treating Savannah
River Mixed Waste |
8034.pdf |
|
D35 |
Hanford Fuel Development Laboratory
Deactivated |
8035.pdf |
|
D36 |
Monitoring and Inspection of Low-Level
Radioactive Waste Stored at Nuclear Power Plants |
8036.pdf |
|
D37 |
Dry Transfer System for Spent Fuel:
Project Report |
8037.pdf |
|
D38 |
Rocky Flats Cleanup Agreement |
8038.pdf |
|
D39 |
LLW Management Information is
Available on the Web |
8039.pdf |
|
D40 |
DOE Agrees to Pick Up Tab for FSV Fuel
Storage |
8040.pdf |
|
D41 |
The DOE's Environmental Cleanup
Efforts |
8041.pdf |
|
D42 |
Shipping of Spent Research Reactor
Fuel |
8042.pdf |
| |
Documents from the Job Database |
45101.pdf |