Development of a mechanistic source term approach for liquid-fueled Molten Salt Reactors

Technical Report · Mon Jul 01 04:00:00 EDT 2019

DOI:https://doi.org/10.2172/1571235· OSTI ID:1571235

Jerden, James ^[1]; Grabaskas, David ^[2]; Bucknor, Matthew ^[2]

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1. Argonne National Lab. (ANL), Argonne, IL (United States). Chemical and Fuel Cycle Technologies Div.
2. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Div.

In addition to the significant progress being made in accident analyses for some molten salt reactor (MSR) concepts, there remains a need for a thorough, step-by-step source term analyses that includes parametric sensitivity analyses and trial calculations. This report provides a basis for developing an MSR source term model by examining the successful methodology used in the sodium fast reactor (SFR) mechanistic source term work presented by Grabaskas et al., [2016a]. Useful risk analyses tools currently in use for developing MSR source term analyses are also summarized, such as those developed for the European Safety Assessment of the Molten Salt Fast Reactor (SAMOFAR) project. Based on the analyses summarized in this report, a pathway is recommended for a rigorous and technology-neutral MSR source term analysis in the U.S. This report is submitted in fulfillment of Advanced Reactor Technologies, Molten Salt Reactor Campaign, Salt Chemistry work package AT-19AN04060104, milestone number M4AT-19AN040601043.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1571235
• Report Number(s): ANL/CFCT--19/4; 153329
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING