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Verification of the Transient Fission Matrix Combination Method in the C5G7-TD Benchmark.

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Title: Verification of the Transient Fission Matrix Combination Method in the C5G7-TD Benchmark.
Authors: Li, Yuehang1,2 (AUTHOR), He, Donghao1,2 (AUTHOR) donghaohe@sjtu.edu.cn, Liu, Xiaojing1,2 (AUTHOR), Pan, Qingquan1,2 (AUTHOR)
Source: Nuclear Science & Engineering. May2026, Vol. 200 Issue 5, p1118-1135. 18p.
Subject Terms: *Transient analysis, *Control elements (Nuclear reactors), *Computer performance, *Light water reactors, *Neutron transport theory
Abstract: The Transient Fission Matrix Combination (TFMC) method is a novel hybrid algorithm that performs transient neutron transport calculations with high fidelity and computational efficiency. In this paper, we verify the TFMC method using the control rod insertion/withdrawal C5G7-TD benchmark. The TD4 test case involves five complex control rod movement patterns in a four-assembly light water reactor model. On 20 parallel cores, each 16-s transient simulation completes in approximately 2 min (excluding database generation time). The computed total power and power distributions agree closely with reference results in all cases. These findings demonstrate the TFMC method's potential as an efficient and accurate tool for transient neutron transport simulations. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
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  Availability: 0
Header DbId: enr
DbLabel: Energy & Power Source
An: 192771854
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Label: Title
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  Data: Verification of the Transient Fission Matrix Combination Method in the C5G7-TD Benchmark.
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  Data: <searchLink fieldCode="AR" term="%22Li%2C+Yuehang%22">Li, Yuehang</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22He%2C+Donghao%22">He, Donghao</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<i> donghaohe@sjtu.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Liu%2C+Xiaojing%22">Liu, Xiaojing</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Pan%2C+Qingquan%22">Pan, Qingquan</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Science+%26+Engineering%22">Nuclear Science & Engineering</searchLink>. May2026, Vol. 200 Issue 5, p1118-1135. 18p.
– Name: Subject
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  Data: *<searchLink fieldCode="DE" term="%22Transient+analysis%22">Transient analysis</searchLink><br />*<searchLink fieldCode="DE" term="%22Control+elements+%28Nuclear+reactors%29%22">Control elements (Nuclear reactors)</searchLink><br />*<searchLink fieldCode="DE" term="%22Computer+performance%22">Computer performance</searchLink><br />*<searchLink fieldCode="DE" term="%22Light+water+reactors%22">Light water reactors</searchLink><br />*<searchLink fieldCode="DE" term="%22Neutron+transport+theory%22">Neutron transport theory</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: The Transient Fission Matrix Combination (TFMC) method is a novel hybrid algorithm that performs transient neutron transport calculations with high fidelity and computational efficiency. In this paper, we verify the TFMC method using the control rod insertion/withdrawal C5G7-TD benchmark. The TD4 test case involves five complex control rod movement patterns in a four-assembly light water reactor model. On 20 parallel cores, each 16-s transient simulation completes in approximately 2 min (excluding database generation time). The computed total power and power distributions agree closely with reference results in all cases. These findings demonstrate the TFMC method's potential as an efficient and accurate tool for transient neutron transport simulations. [ABSTRACT FROM AUTHOR]
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=enr&AN=192771854
RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1080/00295639.2025.2510708
    Languages:
      – Code: eng
        Text: English
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      Pagination:
        PageCount: 18
        StartPage: 1118
    Subjects:
      – SubjectFull: Transient analysis
        Type: general
      – SubjectFull: Control elements (Nuclear reactors)
        Type: general
      – SubjectFull: Computer performance
        Type: general
      – SubjectFull: Light water reactors
        Type: general
      – SubjectFull: Neutron transport theory
        Type: general
    Titles:
      – TitleFull: Verification of the Transient Fission Matrix Combination Method in the C5G7-TD Benchmark.
        Type: main
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            NameFull: Li, Yuehang
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            NameFull: He, Donghao
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            NameFull: Liu, Xiaojing
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            NameFull: Pan, Qingquan
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            – D: 01
              M: 05
              Text: May2026
              Type: published
              Y: 2026
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              Value: 200
            – Type: issue
              Value: 5
          Titles:
            – TitleFull: Nuclear Science & Engineering
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