Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division
Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 7LiF-BeF2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7). Advanced Reactor Technologies Program
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1328309
- Report Number(s):
- ORNL/TM--2016/399; RC0424000; NERC037
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BERYLLIUM FLUORIDES
CROSS SECTIONS
ENERGY DEPENDENCE
EXPERIMENT DESIGN
FLIBE
LITHIUM FLUORIDES
LR-0 REACTOR
MOLTEN SALT COOLED REACTORS
MOLTEN SALT FUELED REACTORS
MSRE REACTOR
NEUTRON SPECTRA
REACTOR PHYSICS
SENSITIVITY ANALYSIS
TEMPERATURE RANGE 0400-1000 K
THERMAL NEUTRONS