Nuclear Safety [Vol. 33, No. 4, October-December 1992]
GENERAL SAFETY CONSIDERATIONS: 499 Technical Note: Nuclear Regulatory Commission’s Examination Question Bank System, C. L Jensen and N. L. Skinner; 506 Report on the Specialists’ Meeting on Passive and Active Safety Features of Liquid-Metal Fast Breeder Reactors Organized by the International Atomic Energy Agency at Oarai Engineering Centre of Power Reactor and Nuclear Development Corporation, Japan, November 5-7,1991, S. R. Paranjpe; ACCIDENT ANALYSIS: 514 A Review of Hydrogen Production During Melt/Water Interaction in LWRs, D. F. Fletcher, B. D. Turland, and S. P. A. Lawrence; 535 A Review of the U308-Al Reaction as a Potential Heat Source in Research and Test Reactor Accidents, J. L. Snelgrove; CONTROL AND INSTRUMENTATION: 543 Multilevel Interfaces for Power Plant Control Rooms II: A Preliminary Design Space, K. J. Vicente; DESIGN FEATURES: 549 Twenty-Second DOE/NRC Nuclear Air Cleaning and Treatment Conference, R. R. Bellamy, D. W. Moeller, and M. W. First; 562 Book Review: Safety Assessment of Unit 5 (WWER-440/W-213) of the Greifswald Nuclear Power Station, M. H. Fontana; WASTE AND SPENT FUEL MANAGEMENT: 576 Activities Related to Waste and Spent Fuel Management, M. D. Muhlheim and E. G. Silver; OPERATING EXPERIENCES: 586 Analysis of Corrective Actions Applied to Nuclear Power Plant Operations, A. E. Cross; 593 Reactor Shutdown Experience, Compiled by J. W. Cletcher; 596 Operating U.S. Power Reactors, Compiled by M. D. Muhlheim and E. G. Silver; 609 Non-Commercial Power Operating Experience; 614 World Nuclear Performance, Compiled by M. D. Muhlheim; RECENT DEVELOPMENTS: 623 General Administrative Activities, Compiled by M. D. Muhlheim and E. G. Silver; 635 Reports, Standards, and Safety Guides, D. S. Queener; 639 Proposed Rule Changes as of June 30, 1992; ANNOUNCEMENTS: 513 Fourth International Conference on Nuclear Fuel Reprocessing and Waste Management RECOD '94; 585 International Topical Meeting on Advanced Reactors Safety; 622 International Workshop on Implementation of ALARA at Nuclear Power Plants; 648 Short Course on Nuclear Criticality Safety; 648 8th Topical Meeting on Problems in Reactor Physics MEPhi-VOLGA-93; 643 The Authors; 646 Reviewers of Nuclear Safety, Vol. 33
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Operational Performance Technology (OPT) Section
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USNRC
- OSTI ID:
- 6412098
- Report Number(s):
- TPJ-NS--33-No.4
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nuclear Safety [Vol. 33, No. 3, July-September 1992]
Nuclear Safety [Vol. 33, No. 2, April-June 1992]
Nuclear Safety [Vol. 34, No. 2, April-June 1993]
Technical Report
·
Tue Jun 30 20:00:00 EDT 1992
·
OSTI ID:10133890
Nuclear Safety [Vol. 33, No. 2, April-June 1992]
Technical Report
·
Tue Mar 31 19:00:00 EST 1992
·
OSTI ID:6681148
Nuclear Safety [Vol. 34, No. 2, April-June 1993]
Technical Report
·
Wed Mar 31 19:00:00 EST 1993
·
OSTI ID:10129203
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR CLEANING
Accident analysis
BREEDER REACTORS
BWR TYPE REACTORS
CLEANING
CONTROL ROOMS
DESIGN
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
Instrumentation
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
Nuclear Safety
OPERATION
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
RADIOACTIVE WASTE MANAGEMENT
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REGULATIONS
RESEARCH AND TEST REACTORS
SAFETY
SPENT FUELS
THERMAL REACTORS
Technical Progress Journal
WASTE MANAGEMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS
Waste and spent fuel management
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR CLEANING
Accident analysis
BREEDER REACTORS
BWR TYPE REACTORS
CLEANING
CONTROL ROOMS
DESIGN
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
Instrumentation
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
Nuclear Safety
OPERATION
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
RADIOACTIVE WASTE MANAGEMENT
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REGULATIONS
RESEARCH AND TEST REACTORS
SAFETY
SPENT FUELS
THERMAL REACTORS
Technical Progress Journal
WASTE MANAGEMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS
Waste and spent fuel management