Published January 2008 | Version v1
Journal article

Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case

  • 1. Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393 (Japan)

Description

For the transition phase analysis of core disruptive accidents, the development of a three-dimensional reactor safety analysis code, SIMMER-IV, has been carried out based on the technology of the two-dimensional SIMMER-III code. The world first application of SIMMER-IV to a small-sized sodium-cooled fast reactor has also been attempted to clarify event progression in the early stage of the transition phase. This SIMMER-IV calculation is compared to the two-dimensional case calculated by SIMMER-III, neglecting the presence of control rod guide tubes. The present analysis with the three-dimensional representation suggests that the conventional scenario leading to rather early high-mobility fuel pool formation is unrealistic and the degraded core tends to keep low mobility in the early stage of transition phase

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2007.04.015

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2007.04.015;
PII
S0029-5493(07)00364-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
1
Journal Page Range
p. 66-73
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.