Characteristic test of initial HTTR core

Naoki Nojiri; Satoshi Shimakawa; Nozomu Fujimoto; Minoru Goto

doi:10.1016/j.nucengdes.2004.08.015

Characteristic test of initial HTTR core

Naoki Nojiri, Satoshi Shimakawa, Nozomu Fujimoto, Minoru Goto

Research output: Contribution to journal › Article › peer-review

19 Citations (Scopus)

Abstract

This paper describes the results of core physics test in start-up and power-up of the HTTR. The tests were conducted in order to ensure performance and safety of the high temperature gas cooled reactor, and was carried out to measure the critical approach, the excess reactivity, the shutdown margin, the control rod worth, the reactivity coefficient, the neutron flux distribution and the power distribution. The expected core performance and the required reactor safety characteristics were verified from the results of measurements and calculations.

Original language	English
Pages (from-to)	283-290
Number of pages	8
Journal	Nuclear Engineering and Design
Volume	233
Issue number	1-3
DOIs	https://doi.org/10.1016/j.nucengdes.2004.08.015
Publication status	Published - Oct 2004
Externally published	Yes

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering
Materials Science(all)
Safety, Risk, Reliability and Quality
Waste Management and Disposal
Mechanical Engineering

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10.1016/j.nucengdes.2004.08.015

Cite this

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author = "Naoki Nojiri and Satoshi Shimakawa and Nozomu Fujimoto and Minoru Goto",

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AU - Nojiri, Naoki

AU - Shimakawa, Satoshi

AU - Fujimoto, Nozomu

AU - Goto, Minoru

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AB - This paper describes the results of core physics test in start-up and power-up of the HTTR. The tests were conducted in order to ensure performance and safety of the high temperature gas cooled reactor, and was carried out to measure the critical approach, the excess reactivity, the shutdown margin, the control rod worth, the reactivity coefficient, the neutron flux distribution and the power distribution. The expected core performance and the required reactor safety characteristics were verified from the results of measurements and calculations.

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ER -

Characteristic test of initial HTTR core

Abstract

All Science Journal Classification (ASJC) codes

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