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Nuclear Technology Volume 206, 2020 - Issue sup1: Special issue on the Kilopower Project, Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Test
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Technical Papers – Selected papers from Kilopower/KRUSTY special issue

KRUSTY Experiment: Reactivity Insertion Accident Analysis

Patrick R. McClurea Los Alamos National Laboratory, Los Alamos, New Mexico87545Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0002-7187-5731
ORCID Icon,
David I. Postona Los Alamos National Laboratory, Los Alamos, New Mexico87545
,
Steven D. Clementa Los Alamos National Laboratory, Los Alamos, New Mexico87545
,
Louis Restrepob Atkins Nuclear Secured, Albuquerque, New Mexico87110
,
Robert Millerb Atkins Nuclear Secured, Albuquerque, New Mexico87110
&
Manny Negretec Mission Support and Test Services, Las Vegas, Nevada89030
Pages S43-S55 | Received 07 Oct 2019, Accepted 23 Jan 2020, Published online: 04 Jun 2020

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Mohammad Allaf, Koji Okamoto, Shunichi Suzuki & Nejdet Erkan. (2023) Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses. Journal of Nuclear Science and Technology 60:8, pages 881-899.
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Nicholas Thompson, Rene Sanchez, Joetta Goda, Kelsey Amundson, Theresa Cutler, Travis Grove, David Hayes, Jesson Hutchinson, Cole Kostelac, George McKenzie, Alexander McSpaden, William Myers & Jessie Walker. (2021) A New Era of Nuclear Criticality Experiments: The First 10 Years of Comet Operations at NCERC. Nuclear Science and Engineering 195:sup1, pages S17-S36.
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Vedant K. Mehta, Michael W. D. Cooper, Robert B. Wilkerson, Dan Kotlyar, Dasari V. Rao & Sven C. Vogel. (2021) Evaluation of Yttrium Hydride (δ-YH2-) Thermal Neutron Scattering Laws and Thermophysical Properties. Nuclear Science and Engineering 195:6, pages 563-577.
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David I. Poston, Marc A. Gibson, Rene G. Sanchez & Patrick R. McClure. (2020) Results of the KRUSTY Nuclear System Test. Nuclear Technology 206:sup1, pages S89-S117.
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David I. Poston, Marc A. Gibson, Thomas Godfroy & Patrick R. McClure. (2020) KRUSTY Reactor Design. Nuclear Technology 206:sup1, pages S13-S30.
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Articles from other publishers (11)

D.Y. Cui, X.X. Li, Y. Dai, Y. Zou, J.G. Chen & X.Z. Cai. (2024) Accident scenario analysis and control scheme design for a micro Molten Salt Reactor. Progress in Nuclear Energy 172, pages 105208.
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Ziang Guo, Limin Liu, Ziyin Liu & Hanyang Gu. (2024) Development and application of a transient analysis code for heat pipe cooled reactor systems. Nuclear Engineering and Design 419, pages 112979.
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M. Yayan Adi Putra, Andang Widi Harto & Alexander Agung. Neutronic analysis of hydride microreactor fuelled with UH3 and ThC. Neutronic analysis of hydride microreactor fuelled with UH3 and ThC.
Wu Wang, Kaiwen Li, Yuchuan Guo, Conglong Jia, Zeguang Li & Kan Wang. (2023) Research on the calculation method of sensitivity coefficients of reactor power to material density based on Monte Carlo perturbation theory. Nuclear Engineering and Technology 55:12, pages 4685-4694.
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Yuchuan Guo, Zilin Su, Zeguang Li, Jiyang Yu & Kan Wang. (2023) Research on the effect of heat pipe temperature oscillation on heat pipe cooled reactor operation. Annals of Nuclear Energy 182, pages 109587.
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Nicholas W. Thompson, Alexis Maldonado, Theresa E. Cutler, Holly R. Trellue, Kelsey M. Amundson, Venkateswara Rao Dasari, Joetta M. Goda, Travis J. Grove, David K. Hayes, Jesson D. Hutchinson, Hadyn M. Kistle, Cole M. Kostelac, Juliann R. Lamproe, Christopher Matthews, George McKenzie, Garrett E. McMath, Alexander T. McSpaden, Rene G. Sanchez, Kristin N. Stolte, Jessie L. Walker, Robert Weldon & Nicholas H. Whitman. (2023) The National Criticality Experiments Research Center and its role in support of advanced reactor design. Frontiers in Energy Research 10.
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A. Nuttin, N. Capellan, S. David, X. Doligez & O. Méplan. (2023) Development and dual validation on a transient inspired by KRUSTY of the sNDM diffusion method for easy, MC-based, core analysis. Annals of Nuclear Energy 180, pages 109469.
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D.Y. Cui, X.X. Li, Y. Dai, G. Hu, X.Z. Cai, Y. Zou & J.G. Chen. (2022) An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR). Progress in Nuclear Energy 151, pages 104326.
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Vedant K. Mehta, Jerawan Armstrong, Dasari V. Rao & Dan Kotlyar. (2022) Capturing multiphysics effects in hydride moderated microreactors using MARM. Annals of Nuclear Energy 172, pages 109067.
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Yuchuan Guo, Zilin Su, Zeguang Li & Kan Wang. (2022) The Super Thermal Conductivity Model for High-Temperature Heat Pipe Applied to Heat Pipe Cooled Reactor. Frontiers in Energy Research 10.
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YuChuan Guo, ZeGuang Li, Kan Wang & ZiLin Su. (2021) A transient multiphysics coupling method based on OpenFOAM for heat pipe cooled reactors. Science China Technological Sciences.
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