Published April 1992 | Version v1
Report

Analysis of the KUCA MEU experiments using the ANL code system

  • 1. Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
  • 2. Argonne National Lab., IL (United States)

Description

Critical experiments using MEU fuel in the KUCA, a light-water-moderated and heavy-water-reflected single-core, were started in May 1981. This paper provides some results on the analysis of the KUCA critical experiments using the ANL code system. The critical mass for HEU and MEU single-cores and the boron burnable-poison effects for MEU cores were analysed. Five-group constants were generated using the EPRI-CELL code and two dimensional diffusion calculations were performed using the DIF3D code. For the analysis on the critical mass, a two-dimensional finite-element diffusion code (2D-FEM-KUR) was also applied and the results compared with the DIF3D (2D) code. (author). 17 refs, 9 figs, 4 tabs

Part of:
Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)

Additional details

Publishing Information

Imprint Title
Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)
Imprint Pagination
368 p.
Journal Page Range
p. 183-192.
ISSN
1011-4289
Report number
IAEA-TECDOC--643(v.3)

Optional Information