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Title: Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS

Abstract

Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS have been conducted. In this work, fission cross section resulted from MCNP6 prediction will be compared with result from TALYS calculation. MCNP6 with its event generator CEM03.03 and LAQGSM03.03 have been validated and verified for several intermediate and heavy nuclides fission reaction data and also has a good agreement with experimental data for fission reaction that induced by photons, pions, and nucleons at energy from several ten of MeV to about 1 TeV. The calculation that induced within TALYS will be focused mainly to several hundred MeV for actinide and sub-actinide nuclides and will be compared with MCNP6 code and several experimental data from other evaluator.

Authors:
 [1]; ; ;  [2]
  1. Department of Physics, Sunan Gunung Djati State Islamic University Bandung, Jl. A.H Nasution No. 105 Cibiru, Bandung (Indonesia)
  2. Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa No. 10 Bandung 40132 (Indonesia)
Publication Date:
OSTI Identifier:
22307850
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1615; Journal Issue: 1; Conference: ICANSE 2013: 4. international conference on advances in nuclear science and engineering, Denpasar, Bali (Indonesia), 16-19 Sep 2013; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; ACTINIDE NUCLEI; COMPARATIVE EVALUATIONS; CROSS SECTIONS; FISSION; M CODES; MEV RANGE; MONTE CARLO METHOD; NUCLEONS; PHOTONS; PIONS; T CODES; TEV RANGE

Citation Formats

Perkasa, Y. S., Waris, A., E-mail: awaris@fi.itb.ac.id, Kurniadi, R., E-mail: awaris@fi.itb.ac.id, and Su'ud, Z., E-mail: awaris@fi.itb.ac.id. Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS. United States: N. p., 2014. Web. doi:10.1063/1.4895873.
Perkasa, Y. S., Waris, A., E-mail: awaris@fi.itb.ac.id, Kurniadi, R., E-mail: awaris@fi.itb.ac.id, & Su'ud, Z., E-mail: awaris@fi.itb.ac.id. Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS. United States. doi:10.1063/1.4895873.
Perkasa, Y. S., Waris, A., E-mail: awaris@fi.itb.ac.id, Kurniadi, R., E-mail: awaris@fi.itb.ac.id, and Su'ud, Z., E-mail: awaris@fi.itb.ac.id. Tue . "Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS". United States. doi:10.1063/1.4895873.
@article{osti_22307850,
title = {Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS},
author = {Perkasa, Y. S. and Waris, A., E-mail: awaris@fi.itb.ac.id and Kurniadi, R., E-mail: awaris@fi.itb.ac.id and Su'ud, Z., E-mail: awaris@fi.itb.ac.id},
abstractNote = {Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS have been conducted. In this work, fission cross section resulted from MCNP6 prediction will be compared with result from TALYS calculation. MCNP6 with its event generator CEM03.03 and LAQGSM03.03 have been validated and verified for several intermediate and heavy nuclides fission reaction data and also has a good agreement with experimental data for fission reaction that induced by photons, pions, and nucleons at energy from several ten of MeV to about 1 TeV. The calculation that induced within TALYS will be focused mainly to several hundred MeV for actinide and sub-actinide nuclides and will be compared with MCNP6 code and several experimental data from other evaluator.},
doi = {10.1063/1.4895873},
journal = {AIP Conference Proceedings},
number = 1,
volume = 1615,
place = {United States},
year = {Tue Sep 30 00:00:00 EDT 2014},
month = {Tue Sep 30 00:00:00 EDT 2014}
}
  • Nuclear data evaluation for fission cross section and fission yield had been performed by many investigators using different model approximation theoretically. These models are encapsulated and implemented into computer codes to perform more robust nuclear reaction data calculations. TALYS is one of most successful nuclear reaction codes that used to determine fission cross section and fission yield. In this paper, TALYS was used to calculate some fission reaction including Am-241 (n,f), Th-232 (n,f), and U-235 (n,f). These calculations are performed using different set of reaction mechanism and optical model parameter adjustment, such as fission barrier parameter, level density parameter, transmissionmore » mechanism, and so on. Reaction mechanism and parameter adjustment are selected based on reaction characteristics to obtain more accurate and reasonable result. The accuracy of calculation result are heavily depends on the reaction mechanism selection and parameter adjustment. All obtained result will be compared with ENDF nuclear data library. This work implemented as preliminary study for calculation of fission cross section using modified method of level density parameter determination. Further work will be more focused to the primary target, that is calculation of any fission cross section using different level density models where its level density parameter (LDP) is approximated by Thermal wavelength instead of RIPL data .« less
  • Fission cross sections in statistical model of fission are calculated using one of important parameter such as transmission coefficients. This parameter calculated using optical model parameter and level density. There are several models of level density that can be used to predict fission cross section. They are Constant Temperature Model, Fermi Gas Model, Back-Shifted Fermi Gas Model, and Generalized Superfluid Model. In this work, fission cross section would be calculated using two different model of level density, such as Constant Temperature Model Plus Fermi Gas and Generalized Superfluid Model on Th-232 (n,f) fission reaction. Calculation result from two different modelmore » then would be compared with experimental data from ENDF B/VI. Analysis of result would lead to the conclusion of spesific characteristic for each model in every fission cases. This work has became a preliminary study to calculate fission cross section using different set of level density models. Further work will be implemented to calculate similar fission cross section using level density parameter that approximated by Thermal wavelength [see 21].« less
  • Most of the development of the MCNPX/6 burnup capability focused on features that were applied to the Boltzman transport or used to prepare coefficients for use in CINDER90, with little change to CINDER90 or the CINDER90 data. Though a scheme exists for best solving the coupled Boltzman and Bateman equations, the most significant approximation is that the employed nuclear data are correct and complete. Thus, the CINDER90 library file contains 60 different actinide fission yields encompassing 36 fissionable actinides (thermal, fast, high energy and spontaneous fission). Fission reaction data exists for more than 60 actinides and as a result, fissionmore » yield data must be approximated for actinides that do not possess fission yield information. Several types of approximations are used for estimating fission yields for actinides which do not possess explicit fission yield data. The objective of this study is to test whether or not certain approximations of fission yield selection have any impact on predictability of major actinides and fission products. Further we assess which other fission products, available in MCNP6 Tier 3, result in the largest difference in production. Because the CINDER90 library file is in ASCII format and therefore easily amendable, we assess reasons for choosing, as well as compare actinide and major fission product prediction for the H. B. Robinson benchmark for, three separate fission yield selection methods: (1) the current CINDER90 library file method (Base); (2) the element method (Element); and (3) the isobar method (Isobar). Results show that the three methods tested result in similar prediction of major actinides, Tc-99 and Cs-137; however, certain fission products resulted in significantly different production depending on the method of choice.« less
  • Fission cross sections of a range of actinides have been measured at the Los Alamos Neutron Science Center (LANSCE) in support of nuclear energy applications in a wide energy range from sub thermal energies up to 200 MeV. Parallel-plate ionization chambers are used to measure fission cross sections ratios relative to the {sup 235}U standard while incident neutron energies are determined using the time-of-flight method. Recent measurements include the {sup 233,238}U, {sup 239-242}Pu and {sup 243}Am neutron-induced fission cross sections. Obtained data are presented in comparison with existing evaluations and previous data.
  • A measurement of the electron spectrum from the thermal neutron fission of U/sup 235/ is described. From this spectrum the antineutrino spectrum is calculated, and on the basis of the two-component theory of the antineutrino a predicted average cross section for the absorption of antineutrinos by protons is (6.1 the J-57 engin 1) x 10/sup -43/ cm/sup 2/fission. This agrees with the measured cross section of (8.7 the J-57 engin 1.5) x 10/sup -43/ cm/sup 2/ fission. The four-component theory of the antineutrino would have predicted (5.05 the J-57 engin 0.5) x 10/sup -43/ cm/sup 2/fission. (auth)