Control of combustible gas concentrations in containment following a loss-of-coolant accident (Revision 2, November 1978)
Book
·
OSTI ID:6905503
Regulations relating to nuclear reactor containment design and operation are contained in Appendix A of 10 CFR Part 50, specifically in Criterion 35, (Emergency Core Cooling), Criterion 50 (Containment Design Basis) and Criterion 41 (Containment Atmosphere Cleanup), as well as paragraph 50.44 in an amendment to Part 50. This guide describes methods acceptable to the Commission for implementing these regulations for light-water reactor plants with cylindrical, zircaloy-clad oxide fuel.
- OSTI ID:
- 6905503
- Report Number(s):
- REG/G-1.7
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
FLUIDS
GASES
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
REGULATORY GUIDES
STANDARDS
TIN ALLOYS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
FLUIDS
GASES
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
REGULATORY GUIDES
STANDARDS
TIN ALLOYS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS