Published 2011 | Version v1
Miscellaneous

Numerical analysis of JOYO MK-II natural circulation test with fast reactor plant dynamics code super-COPD

  • 1. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)
  • 2. NESI Inc., Hitachinaka, Ibaraki (Japan)

Description

An analysis of JOYO MK-II natural circulation tests has been performed to evaluate the applicability of the fast reactor plant dynamics code super-COPD to natural circulation decay heat removal phenomena. In this analysis, it was found that natural circulation behavior is much influenced by the coolant mixing regime in the upper plenum of the reactor vessel. The predicted transient behaviors of the core outlet coolant temperature and the primary flow rate showed good agreement with the test results by using a variable mesh partitioning method and by setting appropriate mixing volume in the upper plenum region which can include the effect of thermal stratification phenomena on the natural circulation behavior. (author)

Part of:
The 16th national symposium on power and energy systems (SPES 2011)

Additional details

Publishing Information

Imprint Title
The 16th national symposium on power and energy systems (SPES 2011)
Imprint Pagination
512 p.
Journal Page Range
p. 217-218

Conference

Title
16. national symposium on power and energy systems
Acronym
SPES 2011
Dates
23-24 Jun 2011
Place
Suita, Osaka (Japan)

Optional Information

Notes
2 refs., 5 figs., 1 tab.