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Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN.

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Title: Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN.
Authors: Vododokhov, Nikolai1 (AUTHOR) vododokn@mcmaster.ca, Novog, David R.1 (AUTHOR)
Source: Nuclear Science & Engineering. Mar2026, Vol. 200 Issue 3, p679-695. 17p.
Subject Terms: *CANDU reactors, *Risk assessment, *Nuclear accidents, *Monte Carlo method, *Nuclear reactor safety measures, *Nuclear energy safety measures
Geographic Terms: Canada
Abstract: In the nuclear power industry, several design-basis accidents are critical for nuclear power plant design and licensing, with loss-of-coolant accidents (LOCAs) being particularly significant for ensuring safe shutdown, emergency cooling, and adequate containment systems. In CANada Deuterium Uranium (CANDU) reactors, a large-break LOCA causes an immediate power surge due to rapid voiding and the positive void reactivity coefficient, with break location greatly influencing severity. Inlet piping breaks, for example, can cause flow reversal, higher voiding rates, or flow stagnation. Conservative assumptions like double-ended guillotine breaks ensure bounding analyses, but for certain metrics (e.g. CANDU fuel channel integrity), partial inlet breaks may be more restrictive, necessitating critical break searches. Break size is crucial in determining mass loss, reactivity, heat deposition, and post-LOCA cooling, impacting severity and mitigation strategies. The Dynamic Probabilistic Safety Assessment (D-PSA) CANDU LOCA pilot aims to identify the most sensitive parameters in critical scenarios and demonstrate the value of D-PSA for risk-informed methods. Using stochastic generation of input parameters under uncertainty, D-PSA quantifies effective risk mitigation factors. While best-estimate analyses attempt to quantify uncertainty in figures of merit, they often impose restrictive conditions. This study integrates uncertainty analysis with component and human reliability in the D-PSA framework, applying Monte Carlo sampling of TRACE input parameters through the RAVEN framework to evaluate dynamic parameters' impact and compare results with existing CANDU LOCA studies. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
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  Availability: 0
Header DbId: enr
DbLabel: Energy & Power Source
An: 191459070
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN.
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  Data: <searchLink fieldCode="AR" term="%22Vododokhov%2C+Nikolai%22">Vododokhov, Nikolai</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> vododokn@mcmaster.ca</i><br /><searchLink fieldCode="AR" term="%22Novog%2C+David+R%2E%22">Novog, David R.</searchLink><relatesTo>1</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Science+%26+Engineering%22">Nuclear Science & Engineering</searchLink>. Mar2026, Vol. 200 Issue 3, p679-695. 17p.
– Name: Subject
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  Data: *<searchLink fieldCode="DE" term="%22CANDU+reactors%22">CANDU reactors</searchLink><br />*<searchLink fieldCode="DE" term="%22Risk+assessment%22">Risk assessment</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+accidents%22">Nuclear accidents</searchLink><br />*<searchLink fieldCode="DE" term="%22Monte+Carlo+method%22">Monte Carlo method</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+reactor+safety+measures%22">Nuclear reactor safety measures</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+energy+safety+measures%22">Nuclear energy safety measures</searchLink>
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  Data: <searchLink fieldCode="DE" term="%22Canada%22">Canada</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: In the nuclear power industry, several design-basis accidents are critical for nuclear power plant design and licensing, with loss-of-coolant accidents (LOCAs) being particularly significant for ensuring safe shutdown, emergency cooling, and adequate containment systems. In CANada Deuterium Uranium (CANDU) reactors, a large-break LOCA causes an immediate power surge due to rapid voiding and the positive void reactivity coefficient, with break location greatly influencing severity. Inlet piping breaks, for example, can cause flow reversal, higher voiding rates, or flow stagnation. Conservative assumptions like double-ended guillotine breaks ensure bounding analyses, but for certain metrics (e.g. CANDU fuel channel integrity), partial inlet breaks may be more restrictive, necessitating critical break searches. Break size is crucial in determining mass loss, reactivity, heat deposition, and post-LOCA cooling, impacting severity and mitigation strategies. The Dynamic Probabilistic Safety Assessment (D-PSA) CANDU LOCA pilot aims to identify the most sensitive parameters in critical scenarios and demonstrate the value of D-PSA for risk-informed methods. Using stochastic generation of input parameters under uncertainty, D-PSA quantifies effective risk mitigation factors. While best-estimate analyses attempt to quantify uncertainty in figures of merit, they often impose restrictive conditions. This study integrates uncertainty analysis with component and human reliability in the D-PSA framework, applying Monte Carlo sampling of TRACE input parameters through the RAVEN framework to evaluate dynamic parameters' impact and compare results with existing CANDU LOCA studies. [ABSTRACT FROM AUTHOR]
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=enr&AN=191459070
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      – Type: doi
        Value: 10.1080/00295639.2025.2494187
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      – Code: eng
        Text: English
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        PageCount: 17
        StartPage: 679
    Subjects:
      – SubjectFull: CANDU reactors
        Type: general
      – SubjectFull: Risk assessment
        Type: general
      – SubjectFull: Nuclear accidents
        Type: general
      – SubjectFull: Monte Carlo method
        Type: general
      – SubjectFull: Nuclear reactor safety measures
        Type: general
      – SubjectFull: Nuclear energy safety measures
        Type: general
      – SubjectFull: Canada
        Type: general
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      – TitleFull: Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN.
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            NameFull: Vododokhov, Nikolai
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            – D: 01
              M: 03
              Text: Mar2026
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              Y: 2026
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