skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Correlated prompt fission data in transport simulations

Abstract

Detailed information on the fission process can be inferred from the observation, modeling and theoretical understanding of prompt fission neutron and γ-ray observables. Beyond simple average quantities, the study of distributions and correlations in prompt data, e.g., multiplicity-dependent neutron and γ-ray spectra, angular distributions of the emitted particles, n -n, n - γ, and γ - γ correlations, can place stringent constraints on fission models and parameters that would otherwise be free to be tuned separately to represent individual fission observables. The FREYA and CGMF codes have been developed to follow the sequential emissions of prompt neutrons and γ rays from the initial excited fission fragments produced right after scission. Both codes implement Monte Carlo techniques to sample initial fission fragment configurations in mass, charge and kinetic energy and sample probabilities of neutron and γ emission at each stage of the decay. This approach naturally leads to using simple but powerful statistical techniques to infer distributions and correlations among many observables and model parameters. The comparison of model calculations with experimental data provides a rich arena for testing various nuclear physics models such as those related to the nuclear structure and level densities of neutron-rich nuclei, the γ-ray strength functionsmore » of dipole and quadrupole transitions, the mechanism for dividing the excitation energy between the two nascent fragments near scission, and the mechanisms behind the production of angular momentum in the fragments, etc. Beyond the obvious interest from a fundamental physics point of view, such studies are also important for addressing data needs in various nuclear applications. The inclusion of the FREYA and CGMF codes into the MCNP6.2 and MCNPX - PoliMi transport codes, for instance, provides a new and powerful tool to simulate correlated fission events in neutron transport calculations important in nonproliferation, safeguards, nuclear energy, and defense programs. Here, this review provides an overview of the topic, starting from theoretical considerations of the fission process, with a focus on correlated signatures. It then explores the status of experimental correlated fission data and current efforts to address some of the known shortcomings. Numerical simulations employing the FREYA and CGMF codes are compared to experimental data for a wide range of correlated fission quantities. The inclusion of those codes into the MCNP6.2 and MCNPX - PoliMi transport codes is described and discussed in the context of relevant applications. The accuracy of the model predictions and their sensitivity to model assumptions and input parameters are discussed. Lastly, a series of important experimental and theoretical questions that remain unanswered are presented, suggesting a renewed effort to address these shortcomings.« less

Authors:
 [1];  [2];  [3];  [1];  [4];  [5];  [1];  [4];  [1];  [6];  [1];  [4];  [1];  [7];  [1];  [1];  [1];  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States). Nuclear & Chemical Sciences Division; Univ. of California, Davis, CA (United States). Physics Dept.
  3. Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)
  4. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
  5. Univ. of California, Davis, CA (United States). Physics Dept.
  6. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of Massachusetts, Lowell, MA (United States). Dept. of Physics and Applied Physics
  7. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States). Nuclear & Chemical Sciences Division
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1424104
Alternate Identifier(s):
OSTI ID: 1438112
Report Number(s):
LLNL-JRNL-738697; LA-UR-17-28181
Journal ID: ISSN 1434-6001; TRN: US1801903
Grant/Contract Number:  
AC52-07NA27344; AC02-05CH11231; AC52-06NA25396
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
European Physical Journal. A
Additional Journal Information:
Journal Volume: 54; Journal Issue: 1; Journal ID: ISSN 1434-6001
Publisher:
Springer
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Molecular, Atomic and Nuclear Physics; Monte Carlo transport simulations; Nuclear fission

Citation Formats

Talou, P., Vogt, R., Randrup, J., Rising, M. E., Pozzi, S. A., Verbeke, J., Andrews, M. T., Clarke, S. D., Jaffke, P., Jandel, M., Kawano, T., Marcath, M. J., Meierbachtol, K., Nakae, L., Rusev, G., Sood, A., Stetcu, I., and Walker, C. Correlated prompt fission data in transport simulations. United States: N. p., 2018. Web. doi:10.1140/epja/i2018-12455-0.
Talou, P., Vogt, R., Randrup, J., Rising, M. E., Pozzi, S. A., Verbeke, J., Andrews, M. T., Clarke, S. D., Jaffke, P., Jandel, M., Kawano, T., Marcath, M. J., Meierbachtol, K., Nakae, L., Rusev, G., Sood, A., Stetcu, I., & Walker, C. Correlated prompt fission data in transport simulations. United States. doi:10.1140/epja/i2018-12455-0.
Talou, P., Vogt, R., Randrup, J., Rising, M. E., Pozzi, S. A., Verbeke, J., Andrews, M. T., Clarke, S. D., Jaffke, P., Jandel, M., Kawano, T., Marcath, M. J., Meierbachtol, K., Nakae, L., Rusev, G., Sood, A., Stetcu, I., and Walker, C. Wed . "Correlated prompt fission data in transport simulations". United States. doi:10.1140/epja/i2018-12455-0. https://www.osti.gov/servlets/purl/1424104.
@article{osti_1424104,
title = {Correlated prompt fission data in transport simulations},
author = {Talou, P. and Vogt, R. and Randrup, J. and Rising, M. E. and Pozzi, S. A. and Verbeke, J. and Andrews, M. T. and Clarke, S. D. and Jaffke, P. and Jandel, M. and Kawano, T. and Marcath, M. J. and Meierbachtol, K. and Nakae, L. and Rusev, G. and Sood, A. and Stetcu, I. and Walker, C.},
abstractNote = {Detailed information on the fission process can be inferred from the observation, modeling and theoretical understanding of prompt fission neutron and γ-ray observables. Beyond simple average quantities, the study of distributions and correlations in prompt data, e.g., multiplicity-dependent neutron and γ-ray spectra, angular distributions of the emitted particles, n -n, n - γ, and γ - γ correlations, can place stringent constraints on fission models and parameters that would otherwise be free to be tuned separately to represent individual fission observables. The FREYA and CGMF codes have been developed to follow the sequential emissions of prompt neutrons and γ rays from the initial excited fission fragments produced right after scission. Both codes implement Monte Carlo techniques to sample initial fission fragment configurations in mass, charge and kinetic energy and sample probabilities of neutron and γ emission at each stage of the decay. This approach naturally leads to using simple but powerful statistical techniques to infer distributions and correlations among many observables and model parameters. The comparison of model calculations with experimental data provides a rich arena for testing various nuclear physics models such as those related to the nuclear structure and level densities of neutron-rich nuclei, the γ-ray strength functions of dipole and quadrupole transitions, the mechanism for dividing the excitation energy between the two nascent fragments near scission, and the mechanisms behind the production of angular momentum in the fragments, etc. Beyond the obvious interest from a fundamental physics point of view, such studies are also important for addressing data needs in various nuclear applications. The inclusion of the FREYA and CGMF codes into the MCNP6.2 and MCNPX - PoliMi transport codes, for instance, provides a new and powerful tool to simulate correlated fission events in neutron transport calculations important in nonproliferation, safeguards, nuclear energy, and defense programs. Here, this review provides an overview of the topic, starting from theoretical considerations of the fission process, with a focus on correlated signatures. It then explores the status of experimental correlated fission data and current efforts to address some of the known shortcomings. Numerical simulations employing the FREYA and CGMF codes are compared to experimental data for a wide range of correlated fission quantities. The inclusion of those codes into the MCNP6.2 and MCNPX - PoliMi transport codes is described and discussed in the context of relevant applications. The accuracy of the model predictions and their sensitivity to model assumptions and input parameters are discussed. Lastly, a series of important experimental and theoretical questions that remain unanswered are presented, suggesting a renewed effort to address these shortcomings.},
doi = {10.1140/epja/i2018-12455-0},
journal = {European Physical Journal. A},
issn = {1434-6001},
number = 1,
volume = 54,
place = {United States},
year = {2018},
month = {1}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Citation Metrics:
Cited by: 7 works
Citation information provided by
Web of Science

Figures / Tables:

Fig. 1. Fig. 1.: (Color online) (a) Average prompt fission neutron multiplicity data [19,20,21] as a function of the fission fragment mass, ν¯(A), for several actinides. (b) Data on the average prompt fission neutron kinetic energy in the center of mass frame as a function of fission fragment mass, < ϵcm >(A)more » [22,23, 24].« less

Save / Share: