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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| Format: | Thesis |
| Language: | English |
| Published: |
2020
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| Subjects: | |
| Online Access: | http://eprints.usm.my/55113/ http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf |
| _version_ | 1848882991507439616 |
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| author | Omar, Muhammad Rabie |
| author_facet | Omar, Muhammad Rabie |
| author_sort | Omar, Muhammad Rabie |
| building | USM Institutional Repository |
| collection | Online Access |
| 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. |
| first_indexed | 2025-11-15T18:43:42Z |
| format | Thesis |
| id | usm-55113 |
| institution | Universiti Sains Malaysia |
| institution_category | Local University |
| language | English |
| last_indexed | 2025-11-15T18:43:42Z |
| publishDate | 2020 |
| recordtype | eprints |
| repository_type | Digital Repository |
| spelling | usm-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/ http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf |