The MELTSPREAD-1 computer code for the analysis of transient spreading in containments
Creators
Description
Transient spreading of molten core materials is important in the assessment of severe-accident sequences for Mk-I boiling water reactors (BWRs). Of interest is whether core materials are able to spread over the pedestal and drywell floors to contact the containment shell and cause thermally induced shell failure, or whether heat transfer to underlying concrete and overlying water will freeze the melt short of the shell. The development of a computational capability for the assessment of this problem was initiated by Sienicki et al. in the form of MELTSPREAD-O code. Development is continuing in the form of the MELTSPREAD-1 code, which contains new models for phenomena that were ignored in the earlier code. This paper summarizes these new models, provides benchmarking calculations of the relocation model against an analytical solution as well as simulant spreading data, and summarizes the results of a scoping calculation for the full Mk-I system
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 644-646
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-15 Nov 1990.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22060635
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BUBBLES; BWR TYPE REACTORS; CARBON DIOXIDE; CHEMICAL COMPOSITION; CHROMIUM; COMPUTER CALCULATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONCRETES; CONTAINMENT SYSTEMS; CORIUM; FAILURES; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; IRON; M CODES; MELTDOWN; MOLTEN METAL-WATER REACTIONS; ONE-DIMENSIONAL CALCULATIONS; OXIDATION; PROBABILITY; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; TWO-PHASE FLOW; WATER; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; CHEMICAL REACTIONS; CONTAINMENT; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; MATERIALS; MECHANICS; METALS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.