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.