Passive ALWR requirements to prevent containment failure. [Advanced light water reactors]

Technical Report · Sun Dec 01 00:00:00 EST 1991

OSTI ID:5534803

Additon, S L; Blanchard, D P; Leaver, D E; Persinko, D ^[1]

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1. TENERA, L.P., San Jose, CA (United States) TENERA, L.P., Bethesda, MD (United States)

The purpose of this report is to document a systematic evaluation of the Passive Advanced Light Water Reactor (ALWR) design requirements which address severe accident mitigation. This evaluation was performed concurrent with completion of the ALWR Requirements Document to assure the adequacy of these mitigation requirements. The passive plant approach to containment integrity assurance reflects an expansion of the approach established earlier for evolutionary ALWRs. The report identifies containment challenges that might occur coincident with or result from a core damage event, compiles the set of passive ALWR design requirements which addresses each challenge, and evaluates each set of requirements on an integrated basis to confirm that the requirements provide substantial assurance that coincident core damage and containment failure are precluded. Based on past PRAs, a review of pertinent safety functions, severe accident analyses, current regulatory requirements, and reviews by ALWR design personnel, twenty-three (23) potential containment challenges were identified. The report concludes that the relevant ALWR requirements severe to limit the likelihood and magnitude of the challenges, and to assure the capability of the containment to accommodate all challenges which remain potentially risk-significant.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States); TENERA, L.P., San Jose, CA (United States); TENERA, L.P., Bethesda, MD (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5534803
• Report Number(s): DOE/ID-10291; MISC-90120; ON: DE92012356
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT
FAILURES
PWR TYPE REACTORS
REACTOR ACCIDENTS
MITIGATION
ATWS
BLOWDOWN
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT SYSTEMS
CORIUM
DETONATIONS
FAILURE MODE ANALYSIS
HEAT TRANSFER
HYDRAULICS
HYDROGEN
LOSS OF COOLANT
MELTDOWN
PROJECTILES
REACTOR SAFETY
SEISMIC EFFECTS
TORNADOES
ACCIDENTS
BUILDING MATERIALS
DISASTERS
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MATERIALS
MECHANICS
NONMETALS
POWER REACTORS
REACTORS
SAFETY
STORMS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WIND
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled