High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1-March 31, 1980

Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Harrington, R. M.

doi:10.2172/6349816

1980

DOI: 10.2172/6349816

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High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1-March 31, 1980

S.J. Ball¹,

J.C. Cleveland²,

J.C. Conklin³

et al.

Abstract: N~TIC~ This document contains information of a preliminary nature. I~ IS subJect to revision or correction and therefore does not represent a fmal report.

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1990

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Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

Cleveland

1990

Nuclear Technology

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The research repomd here has been conducted at the Oak Ridge National Laboratory for the Nuclear Regulatory Commission's Division of Regulatory Applications of the Office of Nuclear Regulatory Research. Tbe short-tenn thermal response of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) is analyzed for a range of flow and reactivity transients. These transients include loss of forced circulation without scram, spurious withdrawal of a control rod group, moisture ingress, control rod and control rod group ejections, and a rapid core cooling event. For each event analyzed, an event description, a discussion of the analysis approach and assumptions, and results are presented. When possible, results of these analyses are compared with those presented by the designers in the MHTGR Preliinary Safety Information Document and in the MHTGR Probabilistic Risk Assessment. The importance of inherent safety features is illusrrated, and conclusions are presented regarding the safety performance of the MHTGR. Recommendations are made for a more indeptb examination of MHTGR response for some of the analyzed transients. The coupled heat transfer-neutron kinetics model is described in detail in Appendix A.

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Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

Cleveland

1990

Nuclear Technology

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High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1-March 31, 1980

Abstract: N~TIC~ This document contains information of a preliminary nature. I~ IS subJect to revision or correction and therefore does not represent a fmal report.

Cited by 1 publication

References 3 publications

Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

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