Calculating infinitemedium αeigenvalue spectra with Monte Carlo using a transition rate matrix method
The timedependent behavior of the energy spectrum in neutron transport was investigated with a formulation, based on continuoustime Markov processes, for computing α eigenvalues and eigenvectors in an infinite medium. In this study, a research Monte Carlo code called “TORTE” (To Obtain Real Time Eigenvalues) was created and used to estimate elements of a transition rate matrix. TORTE is capable of using both multigroup and continuousenergy nuclear data, and verification was performed. Eigenvalue spectra for infinite homogeneous mixtures were obtained, and an eigenfunction expansion was used to investigate transient behavior of the neutron energy spectrum.
 Authors:

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 Univ. of Michigan, Ann Arbor, MI (United States)
 Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
 Publication Date:
 Grant/Contract Number:
 AC0500OR22725
 Type:
 Accepted Manuscript
 Journal Name:
 Nuclear Engineering and Design
 Additional Journal Information:
 Journal Name: Nuclear Engineering and Design; Journal ID: ISSN 00295493
 Publisher:
 Elsevier
 Research Org:
 Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
 Sponsoring Org:
 USDOE
 Country of Publication:
 United States
 Language:
 English
 Subject:
 73 NUCLEAR PHYSICS AND RADIATION PHYSICS
 OSTI Identifier:
 1223665
 Alternate Identifier(s):
 OSTI ID: 1247414
Betzler, Benjamin R., Kiedrowski, Brian C., Brown, Forrest B., and Martin, William R.. Calculating infinitemedium αeigenvalue spectra with Monte Carlo using a transition rate matrix method. United States: N. p.,
Web. doi:10.1016/j.nucengdes.2015.07.052.
Betzler, Benjamin R., Kiedrowski, Brian C., Brown, Forrest B., & Martin, William R.. Calculating infinitemedium αeigenvalue spectra with Monte Carlo using a transition rate matrix method. United States. doi:10.1016/j.nucengdes.2015.07.052.
Betzler, Benjamin R., Kiedrowski, Brian C., Brown, Forrest B., and Martin, William R.. 2015.
"Calculating infinitemedium αeigenvalue spectra with Monte Carlo using a transition rate matrix method". United States.
doi:10.1016/j.nucengdes.2015.07.052. https://www.osti.gov/servlets/purl/1223665.
@article{osti_1223665,
title = {Calculating infinitemedium αeigenvalue spectra with Monte Carlo using a transition rate matrix method},
author = {Betzler, Benjamin R. and Kiedrowski, Brian C. and Brown, Forrest B. and Martin, William R.},
abstractNote = {The timedependent behavior of the energy spectrum in neutron transport was investigated with a formulation, based on continuoustime Markov processes, for computing α eigenvalues and eigenvectors in an infinite medium. In this study, a research Monte Carlo code called “TORTE” (To Obtain Real Time Eigenvalues) was created and used to estimate elements of a transition rate matrix. TORTE is capable of using both multigroup and continuousenergy nuclear data, and verification was performed. Eigenvalue spectra for infinite homogeneous mixtures were obtained, and an eigenfunction expansion was used to investigate transient behavior of the neutron energy spectrum.},
doi = {10.1016/j.nucengdes.2015.07.052},
journal = {Nuclear Engineering and Design},
number = ,
volume = ,
place = {United States},
year = {2015},
month = {8}
}