Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors

In this research, TRIMON, a multigroup Monte Carlo core management code for TRIGA Mark-II reactors has been developed. Furthermore, TRIMON enables direct empirical fuel burnup consideration, where the fuel burnup effect on reactor criticality is considered independently without the need for an ex...

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Main Author: Omar, Muhammad Rabie
Format: Thesis
Language:English
Published: 2020
Subjects:
Online Access:http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf
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author Omar, Muhammad Rabie
author_facet Omar, Muhammad Rabie
author_sort Omar, Muhammad Rabie
collection USM
description In this research, TRIMON, a multigroup Monte Carlo core management code for TRIGA Mark-II reactors has been developed. Furthermore, TRIMON enables direct empirical fuel burnup consideration, where the fuel burnup effect on reactor criticality is considered independently without the need for an external fuel depletion code. With these capabilities, TRIMON supersedes the current state-of-the-art Monte Carlo codes which are not optimal in the direct fuel burnup consideration, core design consideration and performance. The first validation test of TRIMON shows a good agreement with the experimental results obtained from previous experimental works. Plus, the performance benchmark experiment done in this research proves that the use of homogenized neutron cross section reduces the simulation time. At the second stage of this research, TRIMON code has become the tools to assess the unresolved problem of Monte Carlo criticality calculation. Such an unresolved problem is the slow fission source convergence. In this problem, Monte Carlo researchers must wait for a significant amount of time to let the fission source distribution to settle down and converge to a stationary distribution. This has made the simulation of large and complicated reactor cores become a difficult. As a result, this research results in the development of a new fission source convergence acceleration method which is called the Survive-to-Search (S2S) method. Numerical tests of the S2S method for various slow converging problems using TRIMON demonstrated that the method eliminates up to 87% of the convergence time.
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spelling usm.eprints-551132022-10-04T06:52:18Z http://eprints.usm.my/55113/ Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors Omar, Muhammad Rabie QC1 Physics (General) In this research, TRIMON, a multigroup Monte Carlo core management code for TRIGA Mark-II reactors has been developed. Furthermore, TRIMON enables direct empirical fuel burnup consideration, where the fuel burnup effect on reactor criticality is considered independently without the need for an external fuel depletion code. With these capabilities, TRIMON supersedes the current state-of-the-art Monte Carlo codes which are not optimal in the direct fuel burnup consideration, core design consideration and performance. The first validation test of TRIMON shows a good agreement with the experimental results obtained from previous experimental works. Plus, the performance benchmark experiment done in this research proves that the use of homogenized neutron cross section reduces the simulation time. At the second stage of this research, TRIMON code has become the tools to assess the unresolved problem of Monte Carlo criticality calculation. Such an unresolved problem is the slow fission source convergence. In this problem, Monte Carlo researchers must wait for a significant amount of time to let the fission source distribution to settle down and converge to a stationary distribution. This has made the simulation of large and complicated reactor cores become a difficult. As a result, this research results in the development of a new fission source convergence acceleration method which is called the Survive-to-Search (S2S) method. Numerical tests of the S2S method for various slow converging problems using TRIMON demonstrated that the method eliminates up to 87% of the convergence time. 2020 Thesis NonPeerReviewed application/pdf en http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf Omar, Muhammad Rabie (2020) Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors. PhD thesis, Universiti Sains Malaysia.
spellingShingle QC1 Physics (General)
Omar, Muhammad Rabie
Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title_full Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title_fullStr Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title_full_unstemmed Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title_short Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
title_sort trimon an efficient multigroup monte carlo neutron transport code for triga reactors
topic QC1 Physics (General)
url http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf
work_keys_str_mv AT omarmuhammadrabie trimonanefficientmultigroupmontecarloneutrontransportcodefortrigareactors