Published November 1994 | Version v1
Report

IRR-1 moderator temperature coefficient of reactivity at two different core configurations

  • 1. Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

Description

Experiments designed to measure the effect of coolant moderator temperature on core reactivity in an high enrichment uranium swimming pool type reactor were performed. The moderator temperature coefficient of reactivity αw was obtained and found to be different in two core loadings. The measured a.w of one core loading was -13 pcm/degree C at the temperature range of 23-30 degree C. This value of αw is comparable to the data published by the IAEA. The αw measured in the second core loading was found to be -8 pcm/degree C at the same temperature range. The results were used in a core simulation utilizing the Dynamic Simulator for Nuclear Power Plants. (authors). 4 refs., 5 figs

Part of:
Transactions of the nuclear societies of Israel joint meeting 1994

Additional details

Publishing Information

Imprint Title
Transactions of the nuclear societies of Israel Joint meeting 1994
Imprint Pagination
234 p.
Journal Volume
18
Series
Transactions of the nuclear societies of Israel joint meeting 1994.
Journal Page Range
(Pt.V) p. 18-23.
Report number
INIS-mf--14471

Conference

Title
1994 joint meeting of the nuclear societies of Israel.
Dates
28-29 Nov 1994.
Place
Tel Aviv (Israel).

Optional Information