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Journal of Nuclear Science and Technology Volume 44, 2007 - Issue 5
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ARTICLE

Clad-to-Coolant Heat Transfer in NSRR Experiments

Vincent BESSIRON Institut de Radioprotection et de Sûreté Nucléaire (IRSN) Major Accident Prevention Division, CE Cadarache 13115, Saint Paul lez Durance, BP 3, France
,
Tomoyuki SUGIYAMA Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Tokai-mura, Ibaraki, 319-1195, Japan
&
Toyoshi FUKETA Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Tokai-mura, Ibaraki, 319-1195, Japan
Pages 723-732 | Received 05 Sep 2006, Accepted 26 Jan 2007, Published online: 05 Jan 2012

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Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park & Sang-Ki Moon. (2023) Experimental Analysis of Fast-Transient Flow Boiling in Various Flow Conditions Using Inverse Heat Conduction Calculation Method. Nuclear Science and Engineering 197:10, pages 2711-2722.
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Yong-Seok Choi, Jong-Kuk Park, Byong Guk Jeon, Dong Hoon Kam & Sang-Ki Moon. (2022) Application of inverse heat conduction calculation method for fast-transient flow boiling heat transfer analysis. Journal of Nuclear Science and Technology 59:7, pages 835-850.
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Wade Marcum, Daniel LaBrier, Emory Brown, Yikuan Yan & Nicolas Woolstenhulme. (2020) Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop. Nuclear Technology 206:6, pages 895-910.
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Tomoyuki SUGIYAMA, Yutaka UDAGAWA & Toyoshi FUKETA. (2010) Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions. Journal of Nuclear Science and Technology 47:5, pages 439-448.
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Charles P. Folsom, Robert J. Armstrong, Nicolas E. Woolstenhulme, Austin D. Fleming, Connie M. Hill, Colby B. Jensen & Daniel M. Wachs. (2022) Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nuclear Engineering and Design 397, pages 111919.
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Yikuan Yan, Emory Brown & Wade Marcum. (2022) Experimental study of the transient boiling phenomenon on a vertically placed ribbon. Nuclear Engineering and Design 390, pages 111705.
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Isabelle Guénot-Delahaie, Jérôme Sercombe, Éric Fédérici, Christian Bernaudat, Rodrigue Largenton & Xavier Haller. (2022) Investigation of clad ballooning during NSRR RIA tests using ALCYONE fuel performance code. Journal of Nuclear Materials 562, pages 153584.
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G. Khvostov & A. Gorzel. (2021) FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits. Nuclear Engineering and Technology 53:11, pages 3741-3758.
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V. Scheiff, F. Bergame, J. Sebilleau, P. Ruyer & C. Colin. (2021) Experimental study of steady and transient subcooled flow boiling. International Journal of Heat and Mass Transfer 164, pages 120548.
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Richard Hernandez, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen, John D. Bess, Jacob P. Gorton & Nicholas R. Brown. (2020) Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT. Progress in Nuclear Energy 123, pages 103303.
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Paul Van Uffelen & Giovanni Pastore. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 363 416 .
Soon K. Lee, Maolong Liu, Nicholas R. Brown, Kurt A. Terrani, Edward D. Blandford, Heng Ban, Colby B. Jensen & Youho Lee. (2019) Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. International Journal of Heat and Mass Transfer 132, pages 643-654.
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Grigori Khvostov. (2018) Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA. Nuclear Engineering and Design 328, pages 36-57.
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Isabelle Guénot-Delahaie, Jérôme Sercombe, Thomas Helfer, Patrick Goldbronn, Éric Fédérici, Thomas Le Jolu, Aurore Parrot, Christine Delafoy & Christian Bernaudat. (2018) Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code. Nuclear Engineering and Technology 50:2, pages 268-279.
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Asko Arkoma. (2017) Extending the reactivity initiated accident (RIA) fuel performance code SCANAIR for boiling water reactor (BWR) applications. Nuclear Engineering and Design 322, pages 192-203.
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Miriam Daeubler, Nico Trost, Javier Jimenez, Victor Sanchez, Robert Stieglitz & Rafael Macian-Juan. (2015) Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB. Annals of Nuclear Energy 84, pages 31-44.
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Vincent Georgenthum, Alain Moal & Olivier Marchand. (2014) SCANAIR a transient fuel performance code Part two: Assessment of modelling capabilities. Nuclear Engineering and Design 280, pages 172-180.
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Alain Moal, Vincent Georgenthum & Olivier Marchand. (2014) SCANAIR: A transient fuel performance code. Nuclear Engineering and Design 280, pages 150-171.
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I.C. Sagrado & L.E. Herranz. (2014) Modeling RIA benchmark cases with FRAPTRAN and SCANAIR: A comparative exercise. Nuclear Engineering and Design 278, pages 150-162.
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Roberta Visentini, Catherine Colin & Pierre Ruyer. (2014) Experimental investigation of heat transfer in transient boiling. Experimental Thermal and Fluid Science 55, pages 95-105.
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P. Van Uffelen & M. Suzuki. 2012. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 535 577 .

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