FIFRELIN - TRIPOLI-4 coupling for Monte-Carlo simulations with a fission model. Application to shielding calculations
- 1. Universite Paris-Saclay, Commissariat a l'Energie Atomique et aux Energies Alternatives - CEA, DEN, SERMA, 91191 Gif-sur-Yvette (France)
- 2. Commissariat a l'Energie Atomique et aux Energies Alternatives - CEA, Centre de Cadarache, DEN/CAD/DER/SPRC, 13108 Saint-Paul-Lez-Durance (France)
Description
TRIPOLI-4 is a continuous-energy Monte Carlo transport code dedicated to shielding, reactor physics with or without depletion, criticality safety and nuclear instrumentation. FIFRELIN is a Monte Carlo code that simulates the de-excitation process of primary fission fragments leading to an estimation of prompt fission observables such as neutron/gamma/electron multiplicities and spectra in correlation with fission fragments. The TRIPOLI-4 Monte Carlo transport code and the FIFRELIN code have been coupled by means of external files so that neutron transport can take into account fission distributions (multiplicities and spectra) that are not averaged, as is the case when using evaluated nuclear data libraries. Spectral effects on responses in shielding configurations with fission sampling are then expected. In the present paper, the principle of this coupling is detailed and a comparison between TRIPOLI-4 fission distributions at the emission of fission neutrons is presented when using JEFF-3.1.1 evaluated data or FIFRELIN data generated either through a n/γ-uncoupled mode or through a n/γ-coupled mode. Finally, an application to a modified version of the ASPIS benchmark is performed and the impact of using FIFRELIN data on neutron transport is analyzed. Differences noticed on average reaction rates on the surfaces closest to the fission source are mainly due to the average prompt fission spectrum. Moreover, when working with the same average spectrum, a complementary analysis based on non-average reaction rates still shows significant differences that point out the real impact of using a fission model in neutron transport simulations
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/epjconf/201715306003Additional details
Identifiers
Publishing Information
- Publisher
- EDP Sciences
- Imprint Place
- Les Ulis (France)
- Imprint Title
- EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 2016
- Imprint Pagination
- v. 153 [1590 p.]
- Journal Page Range
- p. 06003.p.1-06003.p.7
Conference
- Title
- 13. international conference on radiation shielding; RPSD-2016: 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society
- Acronym
- ICRS-13
- Dates
- 3-6 Oct 2016
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 51049985
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COUPLING; F CODES; FISSION; FISSION SPECTRA; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; T CODES; VALIDATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; NUCLEAR REACTIONS; SPECTRA; TESTING; TRANSPORT THEORY
Optional Information
- Notes
- 12 refs.; This record replaces 51039538