Published March 2005 | Version v1
Report

Planning of the ATWS simulation tests by using experimental fast reactor JOYO

  • 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
  • 2. NESI Inc., Tokyo (Japan)

Description

A study of passive safety test using JOYO has been carried out to demonstrate the inherent safety of sodium cooled fast reactors. In this study, emphasis was placed on the improvement of the accuracy of plant dynamics calculations. The Mimir-N2 analysis code, developed to analyze JOYO plant dynamics, was selected as the standard code for predicting plant behavior during transients. Mimir-N2 was upgraded to be modified based on the plant data of plant characteristics, natural circulation tests during JOYO MK-II and the manual scram tests and loss of power test, etc. during MK-III performance tests. This year, the analysis of the UTOP and the ULOF tests by the Mimir-N2, which are planned for the passive safety tests, and evaluations of the plant structure response were carried out. As a result, we could plan the future UTOP and the ULOF tests conditions. (author)

Availability note (English)

Available from JST Library (JST: Japan Science and Technology Agency), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX:+81-3-3979-2210 (oversea)

Additional details

Publishing Information

Imprint Pagination
55 p.
Report number
JNC-TN--9410-2005-010