Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments
Historically, radiation transport codes have uncorrelated fission emissions. In reality, the particles emitted by both spontaneous and induced fissions are correlated in time, energy, angle, and multiplicity. This work validates the performance of various current Monte Carlo codes that take into account the underlying correlated physics of fission neutrons, specifically neutron multiplicity distributions. The performance of 4 Monte Carlo codes  MCNP®6.2, MCNP®6.2/FREYA, MCNP®6.2/CGMF, and PoliMi  was assessed using neutron multiplicity benchmark experiments. In addition, MCNP®6.2 simulations were run using JEFF3.2 and JENDL4.0, rather than ENDF/BVII.1, data for ^{239}Pu and ^{240}Pu. The sensitive benchmark parameters that in this work represent the performance of each correlated fission multiplicity Monte Carlo code include the singles rate, the doubles rate, leakage multiplication, and Feynman histograms. Although it is difficult to determine which radiation transport code shows the best overall performance in simulating subcritical neutron multiplication inference benchmark measurements, it is clear that correlations exist between the underlying nuclear data utilized by (or generated by) the various codes, and the correlated neutron observables of interest. This could prove useful in nuclear data validation and evaluation applications, in which a particular moment of the neutron multiplicity distribution is of more interest than the othermore »
 Authors:

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 Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
 Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
 Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
 Publication Date:
 Report Number(s):
 LAUR1731332
Journal ID: ISSN 03064549
 Grant/Contract Number:
 AC5206NA25396; NA0002576
 Type:
 Accepted Manuscript
 Journal Name:
 Annals of Nuclear Energy (Oxford)
 Additional Journal Information:
 Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 120; Journal ID: ISSN 03064549
 Publisher:
 Elsevier
 Research Org:
 Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
 Sponsoring Org:
 USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA20)
 Country of Publication:
 United States
 Language:
 English
 Subject:
 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; fission multiplicity; radiation transport; subcritical benchmark; neutron multiplication
 OSTI Identifier:
 1457278
Arthur, Jennifer, Bahran, Rian, Hutchinson, Jesson, Sood, Avneet, Rising, Michael, and Pozzi, Sara A. Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments. United States: N. p.,
Web. doi:10.1016/j.anucene.2018.05.051.
Arthur, Jennifer, Bahran, Rian, Hutchinson, Jesson, Sood, Avneet, Rising, Michael, & Pozzi, Sara A. Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments. United States. doi:10.1016/j.anucene.2018.05.051.
Arthur, Jennifer, Bahran, Rian, Hutchinson, Jesson, Sood, Avneet, Rising, Michael, and Pozzi, Sara A. 2018.
"Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments". United States.
doi:10.1016/j.anucene.2018.05.051. https://www.osti.gov/servlets/purl/1457278.
@article{osti_1457278,
title = {Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments},
author = {Arthur, Jennifer and Bahran, Rian and Hutchinson, Jesson and Sood, Avneet and Rising, Michael and Pozzi, Sara A.},
abstractNote = {Historically, radiation transport codes have uncorrelated fission emissions. In reality, the particles emitted by both spontaneous and induced fissions are correlated in time, energy, angle, and multiplicity. This work validates the performance of various current Monte Carlo codes that take into account the underlying correlated physics of fission neutrons, specifically neutron multiplicity distributions. The performance of 4 Monte Carlo codes  MCNP®6.2, MCNP®6.2/FREYA, MCNP®6.2/CGMF, and PoliMi  was assessed using neutron multiplicity benchmark experiments. In addition, MCNP®6.2 simulations were run using JEFF3.2 and JENDL4.0, rather than ENDF/BVII.1, data for 239Pu and 240Pu. The sensitive benchmark parameters that in this work represent the performance of each correlated fission multiplicity Monte Carlo code include the singles rate, the doubles rate, leakage multiplication, and Feynman histograms. Although it is difficult to determine which radiation transport code shows the best overall performance in simulating subcritical neutron multiplication inference benchmark measurements, it is clear that correlations exist between the underlying nuclear data utilized by (or generated by) the various codes, and the correlated neutron observables of interest. This could prove useful in nuclear data validation and evaluation applications, in which a particular moment of the neutron multiplicity distribution is of more interest than the other moments. It is also quite clear that, because transport is handled by MCNP®6.2 in 3 of the 4 codes, with the 4th code (PoliMi) being based on an older version of MCNP®, the differences in correlated neutron observables of interest are most likely due to the treatment of fission event generation in each of the different codes, as opposed to the radiation transport.},
doi = {10.1016/j.anucene.2018.05.051},
journal = {Annals of Nuclear Energy (Oxford)},
number = ,
volume = 120,
place = {United States},
year = {2018},
month = {6}
}