Published December 1985 | Version v1
Report

Analysis of core flow deviation caused by the large gaps between horizontal block interfaces

  • 1. Department of Power Reactor Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki

Description

There are various leak flow paths between blocks in the experimental VHTR core. Especially, leak flow in the gap between horizontal surfaces of fuel blocks is called ''crossflow''. Generally, the coolant flows from the fuel channel into the gap between columns. As its results fuel temperature rises. In case of the birth of large gap between horizontal block interfaces, the crossflow caused by it effects significantly on the core flow distribution, core temperature distribution and F.P. release. In this paper, the horizontal core offset between the core upper structure and the core support structure is postulated as the cause of occurrence of large horizontal gap at fuel column. A prediction method of large horizontal gaps between blocks, and analytical method and results of core flow distribution are discussed. Analytical results of core behavior in the core flow deviation caused by the gaps between horizontal block interfaces are also presented. Evaluation of fission product release depending on the flow distribution change is also carried out. (author)

Part of:
Gas-cooled reactor safety and accident analysis

Additional details

Publishing Information

Imprint Title
Gas-cooled reactor safety and accident analysis
Imprint Pagination
349 p.
Journal Page Range
p. 313-323.
Report number
IAEA-TECDOC--358

Conference

Title
Specialists' meeting on safety and accident analysis for gas-cooled reactors.
Dates
13-15 May 1985.
Place
Oak Ridge, TN (USA).

Optional Information

Notes
5 refs, 9 figs, 3 tabs.