Potential Impacts of Modeling Full Reactor Cores Using Combined Fuel Performance and Thermal Hydraulics Codes

Porter, Ian Edward; Knight, Travis W.; Raynaud, Patrick

doi:10.13182/nt14-100

Cited by 4 publications

(6 citation statements)

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“…For this given core design, the twice burned fuel average discharge exposure is 45.19 GWd/MTU. The typical discharge exposure for a high energy large PWR core (4-loop) is more close to the limit of 62 GWd/MT than what it was achieved in this demonstration design [Porter, 2015].…”

Section: Information Flow From Core Design To Frapconmentioning

confidence: 56%

“…Due to their separate development paths and goals, reactor system codes and fuel performance codes have inconsistent models and interfaces for coupled analyses. For example, a recently published paper on improving the coupled calculations between TRACE and FRAPCON [Porter, 2015] shows quite large uncertainties for key parameters with different models and coupling methods, i.e., up to 20% difference in stored energy, 20% difference for hydrogen content for high burn up fuel rods at the end of third cycle. The root reasons for the differences come from both ends of the simulations.…”

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

“…By using axial dependent cladding surface temperature and coolant pressure for each concerned fuel rod, more accurate results can be obtained from fuel performance codes. Otherwise, not taking account of localized TH conditions can lead to non-conservatism in terms of steady-state fuel rod licensing limits such as ECR and hydrogen uptake [Porter, 2015].…”

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

“…The parameters include cladding creep, fuel swelling/densification, oxide layer thickness, and burn-up dependent material in each axial fuel node. Only using "average" value for each axial fuel node would be misrepresentation of the conditions existing at either the center or the top and bottom of the rod [Porter, 2015].…”

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

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Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

Szilard

Youngblood

Zhang

et al. 2015

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Step 2 Analysis performed: 1) 11 th cycle to identify 8 points in time to initiate the maneuver (load-following); 2) Load following maneuver at each pre-selected points Goals: skewed power shapes for initiating LOCA analyses Used tools: PHISICS/RELAP5-3D in multi-deck modeStep 3Analysis performed: Steady state calculation to migrate from 1 core channel/assembly to 6 channel model used in LOCA analysis Goals: initial conditions in the lumped TH model (6 channels) Used tools: RELAP5-3DStep 4Analysis performed: LOCA transients at each preselected point in time (after the maneuver) Goals: identify the limiting conditions Used tools:

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Section: Information Flow From Core Design To Frapconmentioning

confidence: 56%

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

Section: Best Practices On Coupling Fuels Performance and Systems Anamentioning

confidence: 99%

See 2 more Smart Citations

Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

Szilard

Youngblood

Zhang

et al. 2015

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“…Notable thermal hydraulic coupling with FRAPCON includes a coupling between a customized version of FRAPCON and the thermal hydraulic code TRACE for a quasi-steady state depletion case (Porter et al, 2015). FRAPTRAN has also been coupled with the thermal hydraulic code COBRA-TF and the neutronics code TORT-TD (Magedanz et al, 2015).…”

Section: Introductionmentioning

confidence: 99%

Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations

Blakely

Zhang

Szilard

et al. 2018

Annals of Nuclear Energy

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The LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Labs (INL) is a plug and play, multiphysics environment to be used in support of system level plant transient analysis. New proposed rule changes in LOCA safety regulations (10 CFR 50.46c) require the inclusion of cladding hydrogen content in the evaluation of equivalent cladding reacted (ECR) and peak cladding temperature (PCT). The potential for a future implementation of said rule change motivates the current development of a unique union of core design, system analysis, and fuel performance codes within a framework allowing for uncertainty quantification (UQ). A demonstration of LOTUS capabilities to address this potential need is performed with an integration of the core design code PHISICS, the fuel performance code FRAPCON, and the system analysis code RELAP5-3D. UQ is performed via Wilks' method to compute the one sided 95/95 confidence values of the aforementioned safety metrics. Results demonstrate the benefits of the Multiphysics Best Estimate Plus Uncertainty (MP-BEPU) methodology and provide useful visualization of the limiting cases.

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Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment

Blakely

Zhang

Ban

2018

Annals of Nuclear Energy

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Potential Impacts of Modeling Full Reactor Cores Using Combined Fuel Performance and Thermal Hydraulics Codes

Cited by 4 publications

References 0 publications

Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations

Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment

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