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Journal Articles
Accepted Manuscript
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-21-1161
Published Online: February 4, 2023
Journal Articles
Accepted Manuscript
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1040
Published Online: January 5, 2023
Journal Articles
Accepted Manuscript
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1137
Published Online: January 1, 2023
Journal Articles
Accepted Manuscript
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1038
Published Online: December 16, 2022
Journal Articles
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
Published Online: December 14, 2022
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 1 Overview of components in EBR‐II More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 2 Flow network model of EBR‐II More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 3 Thermal‐hydraulics model of core: ( a ) Radial heat transfer and ( b ) Inter wrapper gap Flow More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 4 Decay heat curve (boundary condition) More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 5 Comparisons of IHX inlet and outlet temperatures in IHTS between S‐COPD analysis and experiment (BOP‐302R) More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 6 Comparisons of IHX inlet and outlet temperatures in IHTS between S‐COPD analysis and experiment (BOP‐301) More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 7 Comparisons of IHX inlet and outlet temperatures in PHTS between S-COPD analysis and experiment (BOP‐302R) More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 8 Comparisons of IHX inlet and outlet temperatures in PHTS between S-COPD analysis and experiment (BOP‐301) More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 9 Temperature distribution around IHX outlet at 50 s calculated by CFD code More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 10 Comparisons of reactor power between S‐COPD analysis and experiment (BOP‐302R) More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 11 Comparisons of reactor power between S‐COPD analysis and experiment (BOP‐301) More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 12 Reactivities simulated by S‐COPD (BOP‐302R) More
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in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 13 Reactivities simulated by S‐COPD (BOP‐301) More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 14 Comparisons of core inlet and outlet temperatures between S‐COPD analysis and experiment (BOP‐302R) More
Image
in Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
> Journal of Nuclear Engineering and Radiation Science
Published Online: December 14, 2022
Fig. 15 Comparisons of core inlet and outlet temperatures between S‐COPD analysis and experiment (BOP‐301) More
