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Title: Phenomena Important in Molten Salt Reactor Simulations

Abstract

The U.S. Nuclear Regulatory Commission (NRC) is preparing for the future licensing of advanced reactors that will be very different from current light water reactors. Part of the NRC preparation strategy is to identify the simulation tools that will be used for confirmatory safety analysis of normal operation and abnormal situations in those reactors. This report advances that strategy for reactors that will use molten salts (MSRs). This includes reactors with the fuel within the salt as well as reactors using solid fuel. Although both types are discussed in this report, the emphasis is on those reactors with liquid fuel because of the perception that solid-fuel MSRs will be significantly easier to simulate. These liquid-fuel reactors include thermal and fast neutron spectrum alternatives. The specific designs discussed in the report are a subset of many designs being considered in the U.S. and elsewhere but they are considered the most likely to submit information to the NRC in the near future. The objective herein, is to understand the design of proposed molten salt reactors, how they will operate under normal or transient/accident conditions, and what will be the corresponding modeling needs of simulation tools that consider neutronics, heat transfer, fluid dynamics,more » and material composition changes in the molten salt. These tools will enable the NRC to eventually carry out confirmatory analyses that examine the validity and accuracy of applicant’s calculations and help determine the margin of safety in plant design.« less

Authors:
 [1];  [2];  [3];  [4]
  1. Brookhaven National Laboratory (BNL), Upton, NY (United States)
  2. Pennsylvania State Univ., University Park, PA (United States)
  3. Independent Consultant, Columbus, OH (United States)
  4. US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
Publication Date:
Research Org.:
Brookhaven National Lab. (BNL), Upton, NY (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22); Nuclear Regulatory Commission/Non-NUREG
OSTI Identifier:
1436452
Report Number(s):
BNL-114869-2017-INRE
DOE Contract Number:  
SC0012704
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Diamond, David J., Brown, Nicholas R., Denning, Richard, and Bajorek, Stephen. Phenomena Important in Molten Salt Reactor Simulations. United States: N. p., 2018. Web. doi:10.2172/1436452.
Diamond, David J., Brown, Nicholas R., Denning, Richard, & Bajorek, Stephen. Phenomena Important in Molten Salt Reactor Simulations. United States. doi:10.2172/1436452.
Diamond, David J., Brown, Nicholas R., Denning, Richard, and Bajorek, Stephen. Sat . "Phenomena Important in Molten Salt Reactor Simulations". United States. doi:10.2172/1436452. https://www.osti.gov/servlets/purl/1436452.
@article{osti_1436452,
title = {Phenomena Important in Molten Salt Reactor Simulations},
author = {Diamond, David J. and Brown, Nicholas R. and Denning, Richard and Bajorek, Stephen},
abstractNote = {The U.S. Nuclear Regulatory Commission (NRC) is preparing for the future licensing of advanced reactors that will be very different from current light water reactors. Part of the NRC preparation strategy is to identify the simulation tools that will be used for confirmatory safety analysis of normal operation and abnormal situations in those reactors. This report advances that strategy for reactors that will use molten salts (MSRs). This includes reactors with the fuel within the salt as well as reactors using solid fuel. Although both types are discussed in this report, the emphasis is on those reactors with liquid fuel because of the perception that solid-fuel MSRs will be significantly easier to simulate. These liquid-fuel reactors include thermal and fast neutron spectrum alternatives. The specific designs discussed in the report are a subset of many designs being considered in the U.S. and elsewhere but they are considered the most likely to submit information to the NRC in the near future. The objective herein, is to understand the design of proposed molten salt reactors, how they will operate under normal or transient/accident conditions, and what will be the corresponding modeling needs of simulation tools that consider neutronics, heat transfer, fluid dynamics, and material composition changes in the molten salt. These tools will enable the NRC to eventually carry out confirmatory analyses that examine the validity and accuracy of applicant’s calculations and help determine the margin of safety in plant design.},
doi = {10.2172/1436452},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {1}
}