An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo capability for BHTR Analysis
Monte Carlo capability has been combined with a production LWR lattice physics code to allow analysis of high temperature gas reactor configurations, accounting for the double heterogeneity due to the TRISO fuel. The Monte Carlo code MCNP5 has been used in conjunction with CPM3, which was the testbench lattice physics code for this project. MCNP5 is used to perform two calculations for the geometry of interest, one with homogenized fuel compacts and the other with heterogeneous fuel compacts, where the TRISO fuel kernels are resolved by MCNP5.
- Research Organization:
- Univ. of Michigan, Ann Arbor, MI (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- FC07-06ID14745
- OSTI ID:
- 970985
- Report Number(s):
- DOE/ID/14745; TRN: US1001122
- Country of Publication:
- United States
- Language:
- English
Similar Records
Feasibility of a Monte Carlo-deterministic hybrid method for fast reactor analysis
Validation of SCALE and the TRITON Depletion Sequence for Gas-Cooled Reactor Analysis
A synergistic combination of the deterministic and Monte Carlo methods for double-heterogeneous problems
Conference
·
Mon Jul 01 00:00:00 EDT 2013
·
OSTI ID:970985
+1 more
Validation of SCALE and the TRITON Depletion Sequence for Gas-Cooled Reactor Analysis
Conference
·
Tue Jan 01 00:00:00 EST 2008
·
OSTI ID:970985
A synergistic combination of the deterministic and Monte Carlo methods for double-heterogeneous problems
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:970985