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Title: Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments

Abstract

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 JEFF-3.2 and JENDL-4.0, rather than ENDF/B-VII.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 othermore » 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.« less

Authors:
 [1];  [2];  [2];  [2];  [2];  [3]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of Michigan, Ann Arbor, MI (United States)
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Univ. of Michigan, Ann Arbor, MI (United States)
Publication Date:
Research Org.:
Univ. of Michigan, Ann Arbor, MI (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1564315
Alternate Identifier(s):
OSTI ID: 1457278; OSTI ID: 1798644
Report Number(s):
LA-UR-17-31332
Journal ID: ISSN 0306-4549; TRN: US2210703
Grant/Contract Number:  
NA0002534; AC52-06NA25396; NA0002576
Resource Type:
Published Article
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 120; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; fission multiplicity; radiation transport; subcritical benchmark; neutron multiplication

Citation Formats

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., 2018. 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. https://doi.org/10.1016/j.anucene.2018.05.051
Arthur, Jennifer, Bahran, Rian, Hutchinson, Jesson, Sood, Avneet, Rising, Michael, and Pozzi, Sara A. Thu . "Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments". United States. https://doi.org/10.1016/j.anucene.2018.05.051.
@article{osti_1564315,
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 JEFF-3.2 and JENDL-4.0, rather than ENDF/B-VII.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}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.anucene.2018.05.051

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Works referenced in this record:

Prompt Neutron Emission Probabilities Following Spontaneous and Thermal Neutron Fission
journal, September 1985

  • Boldeman, J. W.; Hines, M. G.
  • Nuclear Science and Engineering, Vol. 91, Issue 1
  • DOI: 10.13182/NSE85-A17133

Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP
journal, April 2014


JENDL-4.0: A New Library for Nuclear Science and Engineering
journal, January 2011

  • Shibata, Keiichi; Iwamoto, Osamu; Nakagawa, Tsuneo
  • Journal of Nuclear Science and Technology, Vol. 48, Issue 1
  • DOI: 10.1080/18811248.2011.9711675

Initial MCNP6 Release Overview
journal, December 2012

  • Goorley, T.; James, M.; Booth, T.
  • Nuclear Technology, Vol. 180, Issue 3
  • DOI: 10.13182/NT11-135

Reevaluation of Prompt Neutron Emission Multiplicity Distributions for Spontaneous Fission
journal, October 2008

  • Santi, P.; Miller, M.
  • Nuclear Science and Engineering, Vol. 160, Issue 2
  • DOI: 10.13182/NSE07-85

Revisited
journal, March 1977


Time-of-flight measurements of neutron spectra from the fission of U235, U238 and Pu239
journal, September 1965


Mass distribution in the quasi-mono-energetic neutron-induced fission of 238U
journal, September 2013


ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
journal, December 2011


MCNPX-PoliMi for nuclear nonproliferation applications
journal, December 2012

  • Pozzi, S. A.; Clarke, S. D.; Walsh, W. J.
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 694
  • DOI: 10.1016/j.nima.2012.07.040

Evaluation and Uncertainty Quantification of Prompt Fission Neutron Spectra of Uranium and Plutonium Isotopes
journal, September 2013

  • Rising, M. E.; Talou, P.; Kawano, T.
  • Nuclear Science and Engineering, Vol. 175, Issue 1
  • DOI: 10.13182/NSE12-34

Prompt Fission Neutrons and Gamma Rays in a Monte Carlo Hauser-Feshbach Formalism
journal, January 2013


ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
journal, December 2006


Joint Neutron Noise Measurements on Metallic Reactor Caliban
journal, April 2014


FREYA—A New Monte Carlo Code for Improved Modeling of Fission Chains
journal, April 2013

  • Hagmann, C.; Randrup, J.; Vogt, R.
  • IEEE Transactions on Nuclear Science, Vol. 60, Issue 2
  • DOI: 10.1109/TNS.2013.2251425

MCNP-PoliMi: a Monte-Carlo code for correlation measurements
journal, November 2003

  • Pozzi, Sara A.; Padovani, Enrico; Marseguerra, Marzio
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 513, Issue 3
  • DOI: 10.1016/j.nima.2003.06.012

Development of a research reactor protocol for neutron multiplication measurements
journal, July 2018


Models for a three-parameter analysis of neutron signal correlation measurements for fissile material assay
journal, November 1986

  • Cifarelli, D. M.; Hage, W.
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 251, Issue 3
  • DOI: 10.1016/0168-9002(86)90651-0

Prompt Neutron Emission Multiplicity Distribution and Average Values (Nubar) at 2200 m/s for the Fissile Nuclides
journal, February 1988

  • Holden, Norman E.; Zucker, Martin S.
  • Nuclear Science and Engineering, Vol. 98, Issue 2
  • DOI: 10.13182/NSE88-A28498

Distributions of Fission Neutron Numbers
journal, November 1957


Fission Reaction Event Yield Algorithm, FREYA — For event-by-event simulation of fission
journal, June 2015


The Inelastic Scattering of Neutrons
journal, July 1952


New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities
journal, June 1982

  • Madland, David G.; Nix, J. Rayford
  • Nuclear Science and Engineering, Vol. 81, Issue 2
  • DOI: 10.13182/NSE82-5

Works referencing / citing this record:

Results of Three Neutron Diagnosed Subcritical Experiments
journal, December 2018