Molten Salt Reactor Simulation Capability Using MPACT
The recent interest in molten salt reactor technology by the nuclear industry has sparked significant interest in developing modeling and simulation tools for molten salt reactors. The MPACT whole core transport solver has been adapted to address several unique features of molten salt reactors. This paper discusses implementation of a depletion methodology which simulates the mixing of fuel throughout the core, the continuous removal of fission products, and the continuous addition of new fuel into the system. It also presents the methodology used to treat the transport of delayed neutron precursors. These new methods are demonstrated using models based on Transatomic Power Corporation’s molten salt reactor design.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1651421
- Resource Relation:
- Conference: 2017 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017) - Jeju Island, , South Korea - 4/16/2017 4:00:00 AM-4/20/2017 4:00:00 AM
- Country of Publication:
- United States
- Language:
- English
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