Published 1986 | Version v1
Book

Development of a two-dimensional core-wide heat-up code MUFLAR and its application to analysis of TMI-2 core damage behavior

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment

Description

A two-dimensional core-wide heat-up code MUFLAR has been developed, which calculates two-dimensional flow of steam-hydrogen mixture and radial heat transport by thermal radiation between fuel rod groups. Constitutive models are based on those verified through analyses of wide range of experiments. The code has been applied to an analysis of TMI-2 core damage behavior. The calculated results are in good agreement with the results of recent core examinations. The analysis indicates that cross flow has a radial averaging effect on core temperature. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Soc. of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
Imprint Pagination
1191 p.
Journal Page Range
p. 6/41-6/48.

Conference

Title
2. international topical meeting on nuclear power plant thermal hydraulics and operations.
Dates
15-17 Apr 1986.
Place
Tokyo (Japan).