Experimental simulation and theoretical analysis of molten-corium/structure interaction
- 1. Rensselaer Polytechnic Institute, Troy, NY (USA)
Description
In analysis of core degradation in boiling water reactors, two processes are of particular importance: the heatup and melting of the lower core plate in contact with molten fuel and the interaction between molten debris and the lower head and its various penetrations. Accurate modeling of the simultaneous melting/freezing phenomena occurring between molten corium (UO2 mixed with liquefied Zircaloy and steel) and solid structures is very important in predicting the overall consequences of hypothetical reactor accidents. To provide data for the assessment of models developed for the APRIL code, an experimental program based on simulant materials was undertaken at Rensselaer Polytechnic Institute. To identify appropriate simulant materials, extensive comparative and scaling analyses were performed. As a result, two main simulant materials were selected: tetracosane paraffin (the solid) and Wood's metal (the melt). The X-radiography technique that was used in the experiments allowed for visualization of the corium attack and the resultant wall ablation. The results of these measurements were used as the basis for the development of analytical models and for the verification of the various modeling assumptions made
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 751
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085610
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- A CODES; ACCURACY; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CORIUM; EXPERIMENTAL DATA; FLUID FLOW; HEAT TRANSFER; MELTING; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR CORE DISRUPTION; SOLIDIFICATION; STAINLESS STEELS; URANIUM DIOXIDE; X-RAY RADIOGRAPHY; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; COMPUTER CODES; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SIMULATION; STEELS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-891103--.