IVR analysis code development and validation based on three-layer melt pool configuration
Creators
- 1. Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai (China)
Description
Currently when in-vessel retention (IVR) is evaluated, two-layer melt pool model is usually applied for point estimate analysis. After years of intensive study on IVR, it is found that existing code could not simulate three-layer melt pool model accurately. Thus a modular IVR analysis code using three-layer melt pool model, SPIRE, was developed and validated. The results show that the calculation results of SPIRE code have a good agreement with the data from references. Thus the SPIRE code is feasible to perform IVR analysis. Based on simulation results, the heat fluxes at the bottom of the vessel and light metallic layer notably increase in three-layer melt pool configuration compared with two-layer melt pool configuration. According to sensitive analysis, uranium oxidation rate and total mass of stainless steel have larger influence on heat flux distribution and maximum critical heat flux (CHF) ratio. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 52
- Journal Issue
- 5
- Journal Page Range
- p. 912-919
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55027386
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CORIUM; CRITICAL HEAT FLUX; DISTRIBUTION; HEAT; IN-VESSEL RETENTION; LAYERS; OXIDATION; PONDS; SIMULATION; STAINLESS STEELS; URANIUM; VALIDATION
- Descriptors DEC
- ACTINIDES; ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; ELEMENTS; ENERGY; HEAT FLUX; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; METALS; STEELS; SURFACE WATERS; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 8 figs., 3 tabs., 18 refs.; http://dx.doi.org/10.7538/yzk.2017.youxian.0756