The influence of Xe-135m on steady-state xenon worth in thermal molten salt reactors |
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Affiliation: | 1. Nuclear Engineering, The Ohio State University, 281 West Lane Avenue, Columbus, OH, 43210, USA;2. Ultra Safe Nuclear Corporation, 186 Piedra Loop, Los Alamos, NM 87544, USA;3. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST), 291 Daehak-ro, Yuseong-gu, Daejeon 305-701, Republic of Korea;1. Reactor Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, 143995-1113, Iran;2. Faculty of Electrical and Computer Engineering, Kerman Graduate University of Technology, Kerman, Iran;1. The Institute of Applied Energy, 1-14 Nishi- Shinbashi 1-Chome, Minato-ku, Tokyo, 105-0003, Japan;2. Tokyo Institute of Technology, 2-12-1-N1-9 Ookayama, Meguro-ku, Tokyo, 152-8550, Japan;3. Genden Engineering and Service Company, Kanda-Surugadai 2-24 Chiyoda-ku, Tokyo, 101-0062, Japan;1. Department of Engineering, Lancaster University, Lancaster, LA1 4YW, United Kingdom;2. Hybrid Instruments Ltd., Gordon Manley Building, Lancaster Environment Centre, Lancaster University, Lancaster, LA1 4YQ, United Kingdom;3. Pajarito Scientific Corporation, 2976 Rodeo Park Drive East, Sante Fe, NM, 87505, United States |
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Abstract: | There has been a resurgence of interest in fuel-in-salt Molten Salt Reactors (MSR); a number of governments and private companies are currently undertaking efforts to develop and commercialize MSR technology. Recent nuclear models used in the TENDL nuclear data library have estimated the cross section of the metastable state of 135Xe, 135mXe, to have a much larger cross section than the ground state of 135Xe. Thermal MSRs with continual online noble gas stripping of the fuel salt can operate in a regime where 135mXe makes up a notable fraction of the xenon worth, necessitating the implementation of these new cross-sections in the neutronic analysis of these advanced reactor types. To estimate the effect of 135mXe on reactor operation, a simplified mathematical model was produced with one neutron energy group and 135mXe cross section data from the TENDL-2015 nuclear data library. 235U and 233U systems were investigated. It was found that the steady-state xenon reactivity worth was considerably higher for some modes of operation when 135mXe was included in the xenon worth calculations. Based on available literature, it was found that proposed MSR concepts may operate in the modes of operation where 135mXe has a notable impact on steady-state xenon worth. This work highlights the need to include 135mXe in MSR models and the importance of acquiring evaluated cross-sections for 135mXe. |
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Keywords: | Xenon Molten salt reactor Xe-135m TENDL |
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