Verification of the ENDF/B-VII.1 Based MC2-3 Library Rev.1
- Argonne National Laboratory (ANL), Argonne, IL (United States)
The MC2-3 code, developed by Argonne National Laboratory under the DOE-NE NEAMS program, is a multigroup cross section generation code for fast reactor applications. Last year, the ENDF/B-VII.0 (E70) MC2-3 library, which has been extensively used, verified, and validated over a long period, was intensively reverified and updated to support the commercial grade dedication (CGD) requirement of the TerraPower Natrium project. This year, the ENDF/B-VII.1 (E71) MC2-3 library, the preliminary version of which was generated several years ago, was regenerated and rigorously verified to support the Natrium project as well as the completion of verification of the E71 library. The E71 library was verified using the process developed during the verification of the E70 library, including comparisons of cross sections with the NJOY-generated cross sections, comparisons of the resolved resonance cross sections with those using the PEDNF library, and comparison of total cross sections with the sum of partial cross sections. Additional verifications were conducted to ensure that the benchmark problem solutions with the E71 library are reasonable compared to the corresponding Monte Carlo solutions. Furthermore, the E71 gamma library was generated, which includes data for prompt gamma, delayed gamma, and delayed beta as well as neutron and gamma heating. The gamma library was verified at the level of individual isotopes. The EBR-II core solutions from MC2-3/ DIF3D and MCNP were compared, demonstrating that those solutions in terms of k-effective and assembly powers were in good agreement.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 2584417
- Report Number(s):
- ANL-NSE--24-48-Rev.1; 195407
- Country of Publication:
- United States
- Language:
- English
Similar Records
Recent Updates in ETOE-2 and MC2-3
Improved Gamma Yield and Interaction Cross-Section Libraries of MC2-3
Status report on multigroup cross section generation code development for high-fidelity deterministic neutronics simulation system.
Technical Report
·
Thu Sep 30 00:00:00 EDT 2021
·
OSTI ID:1830755
Improved Gamma Yield and Interaction Cross-Section Libraries of MC2-3
Journal Article
·
Fri Jul 01 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:23042834
Status report on multigroup cross section generation code development for high-fidelity deterministic neutronics simulation system.
Technical Report
·
Fri May 16 00:00:00 EDT 2008
·
OSTI ID:1028602