On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems

Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.

Bibliographic Details
Main Author: Walsh, Jonathan A. (Jonathan Alan)
Other Authors: Benoit Forget and Kord S. Smith.
Format: Thesis
Language:eng
Published: Massachusetts Institute of Technology 2017
Subjects:
Online Access:http://hdl.handle.net/1721.1/106700
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author Walsh, Jonathan A. (Jonathan Alan)
author2 Benoit Forget and Kord S. Smith.
author_facet Benoit Forget and Kord S. Smith.
Walsh, Jonathan A. (Jonathan Alan)
author_sort Walsh, Jonathan A. (Jonathan Alan)
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description Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.
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spelling mit-1721.1/1067002019-04-11T03:10:09Z On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems Walsh, Jonathan A. (Jonathan Alan) Benoit Forget and Kord S. Smith. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering. Nuclear Science and Engineering. Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016. This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. Cataloged from student-submitted PDF version of thesis. Includes bibliographical references (pages 203-212). Computational methods for on-the-fly representation and processing of nuclear data within Monte Carlo neutron transport simulations of intermediate and fast spectrum systems are developed and implemented in a continuous-energy Monte Carlo code. First, a capability to compute temperature-dependent unresolved resonance region (URR) cross sections directly from zero-temperature average resonance parameters is presented. The use of this capability in benchmarking both evaluated and processed URR data is demonstrated. Results of this benchmarking lead to a partial resolution of a longstanding discrepancy between experiment and calculation results for a well-known fast critical assembly. Next, an on-the-fly probability table interpolation scheme for computing temperature-dependent URR cross sections is developed and used in analyses which show that interpolation on a relatively coarse temperature mesh (>100 K) can be used to reproduce results obtained with cross sections generated at an exact temperature. This enables the simulation of systems having detailed temperature distributions using probability table data which require significantly less memory than data generated on a fine temperature mesh. Additional methods for use in the investigation of two common approximations that are made in representing URR cross section data are developed. Namely, a multi-level URR cross section calculation capability is used to show that level-level interference effects in elastic scattering cross sections are negligible in many cases of interest. A capability to generate resonance structure in competitive reaction cross sections is used to show that neglecting cross section structure for reactions other than elastic scattering, capture, and fission can lead to non-negligible, unconservative biases (>100 pcm) in criticality safety calculations. The principal underlying assumption of the probability table method is also tested by comparing the results it yields with results that are averaged over many independent simulations, each using a single, independent realization of URR resonance parameters. Unknown URR resonance structure is observed to induce an uncertainty on the multiplication factor for intermediate and fast spectrum systems that is nearly an order of magnitude greater than that which is purely stochastic. This significantly increases the uncertainty to which results of simulations of those systems should be stated. Finally, a procedure for consistent, on-the-fly sampling of temperature-dependent neutron reaction kernels which requires no additional secondary distribution data is presented. It is used to show that Doppler effects may have only a small impact on elastic scattering secondary angular distributions at typical power reactor operating temperatures but can be appreciable at astrophysical temperatures. by Jonathan A. Walsh. Ph. D. 2017-01-30T18:51:14Z 2017-01-30T18:51:14Z 2016 2016 Thesis http://hdl.handle.net/1721.1/106700 969901587 eng MIT theses are protected by copyright. They may be viewed, downloaded, or printed from this source but further reproduction or distribution in any format is prohibited without written permission. http://dspace.mit.edu/handle/1721.1/7582 212 pages application/pdf Massachusetts Institute of Technology
spellingShingle Nuclear Science and Engineering.
Walsh, Jonathan A. (Jonathan Alan)
On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title_full On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title_fullStr On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title_full_unstemmed On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title_short On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems
title_sort on the fly nuclear data processing methods for monte carlo simulations of intermediate and fast spectrum systems
topic Nuclear Science and Engineering.
url http://hdl.handle.net/1721.1/106700
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