Application of transient fuel bundle analysis code FRETA-B to LOCA simulation experiments
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
- 2. Century Research Center Corp., Tokyo (Japan)
Description
Fuel behavior during loss-of-coolant accidents (LOCA) involves two-dimensional phenomena in each elevation of a bundle, arising from the unsymmetrical structure and also such stochastic factors as fuel relocation or uneven coolant flow. The FRETA-B code can calculate heat conduction, deformation and oxidation of the cladding, and internal gas pressure and flow in multiple fuel rods of a bundle, using two-dimensional models. Ex-phases are placed on the treatments of external (rod-to-rod, or rod-to-coolant) radiant heat transfer and ballooning of the cladding. Calculation can proceed beyond the time of rod-to-rod contact. To assess the code, analyses were performed on the ex-pile multi-rod ballooning experiment in JAERI and on the in-pile LOCA simulation experiment in the NRU reactor. The simple and well-defined boundary condition of the ex-pile experiment has produced good agreement between calculation and measurement of the cladding temperatures. The calculation on the in-pile experiment has shown that stochastic factors are dominant over structural ones in determining the distribution of the cladding temperature and deformation. (author)
Additional details
Publishing Information
- Publisher
- Applied Science Publishers.
- Imprint Place
- London (UK)
- ISBN
- 0 85334 217 2
- Imprint Title
- Water reactor fuel element performance computer modelling
- Imprint Pagination
- 710 p.
- Journal Page Range
- p. 631-647.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 15006759
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COOLANTS; DEFORMATION; F CODES; FUEL CANS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LIQUID FLOW; LOSS OF COOLANT; MATHEMATICAL MODELS; SIMULATION; SOLID FUELS; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY SOURCES; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- Imprint:Published in conjunction with Res Mechanica.