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Nuclear Technology Volume 124, 1998 - Issue 3
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Technical Note

Analysis of the Reactivity during a Pressurized Water Reactor Main-Steam-Line-Break Transient

Garry C. GoseComputer Simulation and Analysis, Inc. Idaho Falls, Idaho
,
Thomas J. DownarPurdue University 1290 Nuclear Engineering Building, West Lafayette, Indiana 47907-1290
&
Karl O. OttPurdue University 1290 Nuclear Engineering Building, West Lafayette, Indiana 47907-1290
Pages 284-290 | Published online: 10 May 2017

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Tomasz Kozlowski, R. Matthew Miller, Thomas J. Downar, Douglas A. Barber & Han Gyu Joo. (2004) Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark. Nuclear Technology 146:1, pages 15-28.
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Articles from other publishers (4)

M. Zarei. (2020) A physically based PID controller for the power maneuvering of nuclear reactors. Progress in Nuclear Energy 127, pages 103431.
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Jinfeng Li. (2020) Computational Perturbation Methods for Moderator and Doppler Temperature Coefficients in the European Pressurised Reactor Core Analysis. Computational Perturbation Methods for Moderator and Doppler Temperature Coefficients in the European Pressurised Reactor Core Analysis.
Ge Shao & Xuewu Cao. (2015) Safety analysis of increase in heat removal from reactor coolant system with inadvertent operation of passive residual heat removal at no-load conditions. Nuclear Engineering and Technology 47:4, pages 434-442.
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Hakim Ferroukhi, Omar Zerkak & Rakesh Chawla. (2009) Cross-section modelling effects on pressurised water reactor main steam line break analyses. Annals of Nuclear Energy 36:8, pages 1184-1200.
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