Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor
Creators
- 1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division
- 2. Transatomic Power Corporation, Cambridge, MA (United States)
Description
This status report presents the results from the first phase of the collaboration between Transatomic Power Corporation (TAP) and Oak Ridge National Laboratory (ORNL) to provide neutronic and fuel cycle analysis of the TAP core design through the Department of Energy Gateway for Accelerated Innovation in Nuclear, Nuclear Energy Voucher program. The TAP design is a molten salt reactor using movable moderator rods to shift the neutron spectrum in the core from mostly epithermal at beginning of life to thermal at end of life. Additional developments in the ChemTriton modeling and simulation tool provide the critical moderator-to-fuel ratio searches and time-dependent parameters necessary to simulate the continuously changing physics in this complex system. Results from simulations with these tools show agreement with TAP-calculated performance metrics for core lifetime, discharge burnup, and salt volume fraction, verifying the viability of reducing actinide waste production with this design. Additional analyses of time step sizes, mass feed rates and enrichments, and isotopic removals provide additional information to make informed design decisions. This work further demonstrates capabilities of ORNL modeling and simulation tools for analysis of molten salt reactor designs and strongly positions this effort for the upcoming three-dimensional core analysis.
Availability note (English)
Available from http://info.ornl.gov/sites/publications/files/Pub72176.pdf; PURL: http://www.osti.gov/servlets/purl/1340461/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- ORNL/TM--2016/742
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 48053010
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; ENRICHMENT; FUEL CYCLE; LIFETIME; MODERATORS; MOLTEN SALT REACTORS; NEUTRON SPECTRA; NUCLEAR FUELS; PERFORMANCE; REACTOR CORES; REACTOR DESIGN; REACTOR KINETICS; SPECTRAL SHIFT; TIME DEPENDENCE; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- DESIGN; ENERGY SOURCES; FUELS; KINETICS; MATERIALS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SIMULATION; SPECTRA
Optional Information
- Contract/Grant/Project number
- AC05-00OR22725
- Funding organization
- USDOE Office of Nuclear Energy - NE. Gateway for Accelerated Innovation in Nuclear (GAIN). Nuclear Energy Voucher Program (United States)
- Secondary number(s)
- OSTIID--1340461