Published December 2022 | Version v1
Journal article

Steady-state radiochemical transport model of the molten salt reactor experiment

  • 1. Argonne National Laboratory, Lemont, IL (United States)

Description

A radiochemical transport model of the Molten Salt Reactor Experiment (MSRE) was formulated based on the material derivative featuring system level 1-D flow providing spatial dependence accounting for multiple phenomena including radioactive decay, chemical removal, and fuel depletion across custom volume regions. The steady-state version, which is based on a system of ODE's, can be solved efficiently and is useful for sensitivity studies utilizing Monte Carlo sampling. Accounting for multiple phenomena in a fully coupled model is necessary to understand the complexities of transport and distribution of radionuclides throughout the primary loop of a flowing fuel reactor. (author)

Additional details

Publishing Information

Journal Title
Journal of Radioanalytical and Nuclear Chemistry
Journal Volume
331
Journal Issue
12
Journal Page Range
p. 5247-5257
ISSN
0236-5731
CODEN
JRNCDM

Conference

Title
12. International Conference on Methods and Applications of Radioanalytical Chemistry
Acronym
MARC XII
Dates
3-8 Apr 2022
Place
Kailua-Kona, Hawaii (United States)

INIS

Country of Publication
Hungary
Country of Input or Organization
Hungary
INIS RN
54016847
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; MOLTEN SALT REACTORS; RADIONUCLIDE KINETICS; REMOVAL; SENSITIVITY
Descriptors DEC
KINETICS; REACTORS

Optional Information

Notes
29 refs.