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Journal Articles

Post fission time evolution calculation by FIFRELIN coupled with PHITS and DCHAIN

Ogawa, Tatsuhiko; Litaize, O.*; Mancusi, D.*; Chebboubi, A.*; Serot, O.*

European Physical Journal A, 58(8), p.153_1 - 153_9, 2022/08

 Times Cited Count:0 Percentile:34.54(Physics, Nuclear)

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fission of fissile nuclei. It can predict fission observables such as fragment yields and neutron yields accurately by using experimental data and databases. However, FIFRELIN cannot calculate remnant dose and decay heat considering delayed decay of fission fragments. Moreover, FIFRELIN can predict the energy spectra of neutrons and gammas but further transport calculation required generation of heavy external files. In this study, FIFRELIN was interfaced to radiation transport code PHITS to perform burn up calculation and particle transport calculation. Owing to the burn up calculation, decay heat and remnant dose were calculated for given irradiation condition and cooling period. Interface of particle transport calculation by PHITS and FIFRELIN can perform particle transport simulation based on the source term calculated by FIFRELIN.

Journal Articles

The Joint evaluated fission and fusion nuclear data library, JEFF-3.3

Plompen, A. J. M.*; Cabellos, O.*; De Saint Jean, C.*; Fleming, M.*; Algora, A.*; Angelone, M.*; Archier, P.*; Bauge, E.*; Bersillon, O.*; Blokhin, A.*; et al.

European Physical Journal A, 56(7), p.181_1 - 181_108, 2020/07

 Times Cited Count:234 Percentile:99.41(Physics, Nuclear)

The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu, on $$^{241}$$Am and $$^{23}$$Na, $$^{59}$$Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yileds, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 is excellent for a wide range of nuclear technology applications, in particular nuclear energy.

Journal Articles

EXILL; A High-efficiency, high-resolution setup for $$gamma$$-spectroscopy at an intense cold neutron beam facility

Jentschel, M.*; Blanc, A.*; de France, G.*; K$"o$ster, U.*; Leoni, S.*; Mutti, P.*; Simpson, G.*; Soldner, T.*; Ur, C.*; Urban, W.*; et al.

Journal of Instrumentation (Internet), 12(11), p.P11003_1 - P11003_33, 2017/11

 Times Cited Count:34 Percentile:84.59(Instruments & Instrumentation)

Oral presentation

Extension of fission reaction model FIFRELIN for wider reaction conditions and post processing

Ogawa, Tatsuhiko; Litaize, O.*; Mancusi, D.*; Chebboubi, A.*; Serot, O.*

no journal, , 

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fissions of fissile nuclei. In case of neutron-induced fissions, the compound nucleus always fissioned from an exited state whose excitation energy is sum of the incoming neutron energy and the neutron binding energy. While in the new version, with the multi-chance fission algorithm, the fissioning nuclei can start from higher exited states considering the competition of fission reactions, neutron emission, and gamma emission. When fission is selected in the competition, the partitioning of mass, charge, excitation energy, and angular momentum to the two fission fragments is determined either by the FIFRELIN native algorithm or by GEF. In fission reactions induced by energetic neutrons, pre-fission particle emission reduces the excitation energy of the compound nucleus before fission, leading to a noticeable difference of the final observables such as neutron multiplicity and fission product mass distribution. The other updated feature is the interface to codes handling the post-reaction processes. The energy spectra of neutrons, electrons and photons from fission reactions are output in a format compatible with PHITS, a general-purpose particle transport code. By using this functionality, one can simulate the transport and reactions of particles based on the cross section data and reaction models of PHITS, and the spectra calculated by FIFRELIN. Finally, the other interface developed in this study is nuclide yield output in a format compatible with DCHAIN-SP2014, a burn-up calculation code. This interface is necessary to consider the build-up, which depends on the time structure of the incoming neutron beam as well as the decay during the cooling period.

Oral presentation

Coupling of fission event generator FIFRELIN to radiation transport code PHITS

Ogawa, Tatsuhiko; Litaize, O.*; Mancusi, D.*; Chebboubi, A.*; Serot, O.*

no journal, , 

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fissions of fissile nuclei. In this study, its interfaces to codes handling the post-reaction processes were developed. The energy spectra of neutrons, electrons and photons from fission reactions are output in a format compatible with PHITS, a general-purpose particle transport code. By using this functionality, one can simulate the transport and reactions of particles based on the cross section data and reaction models of PHITS, and the source spectra calculated by FIFRELIN. The other interface developed in this study outputs nuclide yield output in a format compatible with DCHAIN-PHITS, a burn-up calculation code. This interface is necessary to consider the build-up, which depends on the time structure of the incoming neutron beam as well as the decay during the cooling period.

Oral presentation

New results in the modeling of fission and radiative neutron capture with FIFRELIN

Litaize, O.*; Piau, V.*; Chalil, A.*; Ogawa, Tatsuhiko; Chebboubi, A.*; Gook, A.*; Gunsing, F.*; Kessedjian, G.*; Lhuillier, D.*; Mancusi, D.*; et al.

no journal, , 

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fission of fissile nuclei. In this study, its interfaces to radiation transport code PHITS, extension for neutron capture reactions, and a function to calculate neutrinos from fission fragments were developed. In order to extend FIFRELIN for neutron capture reactions, accurate gamma-ray yield was obtained by tuning the level density considering the nuclide species and excitation energy. Accurate neutrino yield was obtained by adopting up-to-date database on the thermal neutron capture state. JAEA developed an interface of FIFRELIN to PHITS to perform new FIFRELIN benchmark using FIFRELIN-DCHAIN joint calculation.

Oral presentation

Development of multi-chance fission module for fission event generator FIFRELIN

Ogawa, Tatsuhiko; Litaize, O.*; Mancusi, D.*; Chebboubi, A.*; Serot, O.*

no journal, , 

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fissions of fissile nuclei and spontaneous fissions. In this study, a reaction module for multi-chance fission was developed. Multi-chance fission reaction are fission reactions preceded by neutron emission owing to the incident neutron energy higher than the fission barrier. For this development, an algorithm to calculate the excitation energy, spin and parity of the compound nucleus was implemented. In addition, a fission width and neutron emission width were calculated by Bohr-Wheeler formula and Hauser-Feshbach formula, respectively. If neutron emission reaction is sampled and the excitation energy reaches below the fission barrier, fission reaction is prohibited and the nucleus is deexcited by evaporation. The prompt fission probability of $$^{240}$$U(n,fission) calculated with these new algorithms, qualitatively agreed with experimental data. By improving the neutron transmission coefficient and level density formalism used in the Hauser-Feshbach calculation to calculate multi-chance fission calculation more accurately.

Oral presentation

Investigation of the structure of $$^{235}$$U(n$$_{th}$$,fission) prompt gamma energy spectrum by FIFRELIN

Ogawa, Tatsuhiko; Litaize, O.*; Mancusi, D.*; Chebboubi, A.*; Serot, O.*

no journal, , 

Thermal fission of U-235 is fundamental for nuclear energy engineering, whose details were observed through neutrons and gamma-rays. Among them, gamma-rays above 8 MeV, which come from immediate gamma deexcitation of fission fragments, were recently measured as a probe to observe fission more directly. The energy spectrum measured by a theoretical model CoH3 (Coupled-Channels Hauser-Feshbach Code) reproduced a peak around 4 MeV and a shoulder from 6 to 8 MeV, however, underestimated the components above 14 MeV. In this study, we used FIFRELIN developed by the French Atomic Energy, Alternative Energy Commission (CEA) to reproduce the gamma-ray energy spectrum. In addition to the peak around 4 MeV and a shoulder from 6 to 8 MeV, gamma spectrum up to 20 MeV was reproduced. This calculation also discovered that the level-density model for fission fragments plays the critical role. It was thus illustrated that FIFRELIN is useful to reproduce the spectra of gamma-ray from fission and investigate the reaction processes responsible for gamma-ray spectrum.

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