Adiabatic equilibrium models for direct containment heating
Description
Probabilistic risk assessment (PRA) studies are being extended to include a wider spectrum of reactor plants than was considered in NUREG-1150. There is a need for simple direct containment heating (DCH) models that can be used for screening studies aimed at identifying potentially significant contributors to overall risk in individual nuclear power plants. This paper presents two adiabatic equilibrium models suitable for the task. The first, a single-cell model, places a true upper bound on DCH loads. This upper bound, however, often far exceeds reasonable expectations of containment loads based on CONTAIN calculations and experiment observations. In this paper, a two cell model is developed that captures the major mitigating feature of containment compartmentalization, thus providing more reasonable estimates of the containment load. Predictions of the equilibrium models are compared with experimental data from the Limited Flight Path test series conducted at Sandia National Laboratories
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 2, Severe accident research; Severe accident policy implementation; Accident management
- Imprint Pagination
- 504 p.
- Journal Page Range
- p. 113-127.
- Report number
- NUREG/CP--0119-Vol.2
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027120
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADIABATIC PROCESSES; BLOWDOWN; BWR TYPE REACTORS; C CODES; COMBUSTION; COMPARTMENTS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; CORIUM; DYNAMIC LOADS; HEAT TRANSFER; HEATING; HYDRAULICS; HYDROGEN; MELTDOWN; MITIGATION; MOLTEN METAL-WATER REACTIONS; PRESSURE VESSELS; PRESSURIZATION; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REGULATIONS; RISK ASSESSMENT; SANDIA LABORATORIES; SCALE MODELS; SCALING LAWS; US NRC
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; CONTAINERS; CONTAINMENT; ELEMENTS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; LAWS; NATIONAL ORGANIZATIONS; NONMETALS; OXIDATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SANDIA NATIONAL LABORATORIES; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--Vol.2.