Published 2017 | Version v1
Book

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/201715306003
Part of:
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

Additional 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