MCNPX, MONK, and ERANOS analyses of the YALINA booster subcritical assembly.
- Nuclear Engineering Division
This paper compares the numerical results obtained from various nuclear codes and nuclear data libraries with the YALINA Booster subcritical assembly (Minsk, Belarus) experimental results. This subcritical assembly was constructed to study the physics and the operation of accelerator-driven subcritical systems (ADS) for transmuting the light water reactors (LWR) spent nuclear fuel. The YALINA Booster facility has been accurately modeled, with no material homogenization, by the Monte Carlo codes MCNPX (MCNP/MCB) and MONK. The MONK geometrical model matches that of MCNPX. The assembly has also been analyzed by the deterministic code ERANOS. In addition, the differences between the effective neutron multiplication factor and the source multiplication factors have been examined by alternative calculational methodologies. The analyses include the delayed neutron fraction, prompt neutron lifetime, generation time, neutron flux profiles, and spectra in various experimental channels. The accuracy of the numerical models has been enhanced by accounting for all material impurities and the actual density of the polyethylene material used in the assembly (the latter value was obtained by dividing the total weight of the polyethylene by its volume in the numerical model). There is good agreement between the results from MONK, MCNPX, and ERANOS. The ERANOS results show small differences relative to the other results because of material homogenization and the energy and angle discretizations.The MCNPX results match the experimental measurements of the {sup 3}He(n,p) reaction rates obtained with the californium neutron source.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- NE
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 1018176
- Report Number(s):
- ANL/NE/JA-68375; TRN: US1103305
- Journal Information:
- Nucl. Eng. Des., Vol. 241, Issue 5 ; May 2011
- Country of Publication:
- United States
- Language:
- ENGLISH
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCURACY
BELARUS
CALIFORNIUM
DELAYED NEUTRON FRACTION
EXPERIMENTAL CHANNELS
FAST REACTORS
IMPURITIES
LIFETIME
LIQUID METALS
MULTIPLICATION FACTORS
NEUTRON FLUX
NEUTRON SOURCES
NEUTRONS
NUCLEAR FUELS
PHYSICS
POLYETHYLENES
PROMPT NEUTRONS
REACTION KINETICS
SPECTRA
WATER