Published 1983 | Version v1
Book

Application of transient fuel bundle analysis code FRETA-B to LOCA simulation experiments

  • 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.

Optional Information

Notes
Imprint:Published in conjunction with Res Mechanica.