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Conference Article: Uncertainties in calculations of nuclear design code system for the high temperature engineering test reactor (HTTR).

Shindo, R.; Yamashita, K.; Murata, I. (Japan Atomic Energy Research Inst., Orai, Ibaraki (Japan). Dept. of HTTR Project)

Abstract

The nuclear design code system for the HTTR consists of one dimensional cell burnup computer code, developed in JAERI and the TWOTRAN-2 transport code. In order to satisfy related design criteria, uncertainty of the calculation was investigated by comparing the calculated and experimental results. The experiments were performed with a graphite moderated critical assembly. It was confirmed that discrepancies between calculations and experiments were small enough to be allowed in the nuclear design of HTTR.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Uncertainties in physics calculations for gas cooled reactor cores. Proceedings of a specialist's meeting held in Villigen, Switzerland, 9-11 May 1990
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--24, pp:81-86