Two-Dimensional Neutronic and Fuel Cycle Analysis of the LEU-Fueled Transatomic Power Molten Salt Reactor

Journal Article · Sat Jul 01 04:00:00 EDT 2017 · Transactions of the American Nuclear Society

OSTI ID:23050352

Betzler, B. R.; Powers, J. J.; Worrall, A. ^[1]; Robertson, S.; Dewan, L.; Massie, M. ^[2]

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1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6170 (United States)
2. Transatomic Power Corporation, One Broadway, 14th Floor, Cambridge, MA 02142 (United States)

A recent Third Way report detailing $1.3 billion in private investment in advanced reactor technology includes several liquid-fueled molten salt reactor (MSR) concepts. Interest in these MSR concepts is driven by the enhanced safety, economic, and promising fuel cycle benefits of these advanced reactor concepts. The US Department of Energy (DOE) Office of Nuclear Energy established the Gateway for Accelerated Innovation in Nuclear (GAIN) to provide private companies pursuing innovative nuclear energy technologies with access to the technical support necessary to move toward commercialization. GAIN activities in 2016 included competitive selection of projects for vouchers to fund applicant-specific work at national laboratories. One of these GAIN small business voucher awards was to Transatomic Power Corporation (TAP) to work with Oak Ridge National Laboratory (ORNL) to perform neutronic and fuel cycle analysis and design of TAP's innovative MSR concept. The initial phase of this project is to perform two-dimensional (2D) analysis with ORNL-developed tools to verify TAP-calculated metrics and to develop an understanding of the effects of fuel feed and isotopic removal rates to prepare for the more complex three-dimensional (3D) analysis in coming phases. Design information was based on the TAP white papers wherever possible. This summary discusses the results of this initial phase of the collaboration between ORNL and TAP.

• OSTI ID: 23050352
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 116; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
DESIGN
FUEL CYCLE
GAIN
MOLTEN SALT REACTORS
NUCLEAR ENERGY
ORNL
REACTOR TECHNOLOGY
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS