The Transfer of Xenon-135 to Molten Salt Reactor Graphite

Author:

Price Terry,Chvala Ondrej1

Affiliation:

1. Walker Department of Mechanical Engineering, The University of Texas at Austin , Austin, TX 78712

Abstract

Abstract The term “Molten salt reactors” refers to a broad class of nuclear reactors that use a molten alkali-halide salt as the primary coolant fluid. This paper pertains to thermal spectrum liquid fuel molten fluoride salt reactors with graphite moderator (MSRs), where the molten salt also dissolves the actinide fuel. Xenon isotope 135,135Xe, is a fission product that is produced during nuclear fission energy production, and it acts as a neutron poison. Due to the circulating nature of the fuel salt in MSRs, there is a qualitative difference in the behavior of 135Xe in an MSR compared to a solid fueled reactor. Some of the 135Xe produced in fission may end up in the pore space of the porous graphite moderator used in an MSR. This paper examines the transfer and storage of 135Xe in MSR graphite. Prior publications are reviewed, the porosity of the MSR graphite is examined, governing equations are detailed, film layer production and destruction are discussed, the graphite/salt interface is explored, transport pathways are considered, transfer processes are exposited, the effect of charged species is examined, the solubility of noble gases in molten fluoride salts is examined, the mass diffusion coefficient in molten salts is explored, and the calculation of mass transfer coefficients is described.

Publisher

ASME International

Reference57 articles.

1. Protection of Graphite From Salt and Gas Permeation in Molten Salt Reactors;J. Nucl. Mater.,2020

2. Robertson, R., 1965, “ ORNL-TM-0728: MSRE Design and Operations Report,” Oak Ridge, TN, Oak Ridge National Laboratory, Report No. ORNL-TM-0728, p. 536.

3. McCoy, H. E., and Weir, J. R., 1967, “ ORNL-TM-1854: Materials Development for Molten-Salt Breeder Reactors,” Report No. ORNL-TM-1854.

4. Moore, J., Godfrey, T., and McElroy, D., 1964, “ ORNL-P-150: Thermal Properties of Grade CGB Graphite,” Oak Ridge, TN, Oak Ridge National Laboratory, Report No. ORNL-P-150.

5. Malinauskas, A., Rutherford, J., and Evans, R., 1967, “ ORNL-4148: Gas Transport in MSRE Moderator Graphite. Part 1: Review of Theory and Counter Diffusion Experiments,” Oak Ridge National Laboratory, Report No. ORNL-4148.

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3