Results 71 to 80 of about 2,939 (182)
Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
Science and Technology of Nuclear Installations, 2016 Helically coiled tube Once-Through Steam Generator (H-OTSG) is one of the key equipment types for small modular reactors. The flow instability of the secondary side of the H-OTSG is particularly serious, because the working condition is in the range of ...
Junwei Hao +7 more
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RELAP5/MOD3.3 Analysis of the Loss of External Power Event with Safety Injection Actuation
Science and Technology of Nuclear Installations, 2018 The code assessment typically comprises basic tests cases, separate effects test, and integral effects tests. On the other hand, the thermal hydraulic system codes like RELAP5/MOD3.3 are primarily intended for simulation of transients and accidents in ...
Andrej Prošek, Marko Matkovič
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Estimate of LOCA-FI plenum pressure uncertainty for a five-ring RELAP5 production reactor model [PDF]
, 1993 The RELAP5/MOD2.5 code (RELAP5) is used to perform best-estimate analyses of certain postulated Design Basis Accidents (DBAs) in SRS production reactors.
Griggs, D. P.
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Architectural Advancements in RELAP5-3D [PDF]
, 2005 As both the computer industry and field of nuclear science and engineering move forward, there is a need to improve the computing tools used in the nuclear industry to keep pace with these changes.
Mesina, Dr. George L.
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Science and Technology of Nuclear Installations, 2010 The behaviour of a parallel-channel natural circulation boiling water reactor under a low-pressure low-power startup condition has been studied numerically (using RELAP5) and compared with its scaled model.
S. P. Lakshmanan, Manmohan Pandey
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Science and Technology of Nuclear Installations, 2016 The latest versions of RELAP5-3D© code allow the simulation of thermodynamic system, using different type of working fluids, that is, liquid metals, molten salt, diathermic oil, and so forth, thanks to the ATHENA code integration.
P. Balestra +3 more
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International Journal of Advanced Nuclear Reactor Design and Technology, 2020 Passive safety systems mostly working on the principles of natural circulation are given much priority in increasing the reliability of reactors’ inherent safety features.
Abbati Zahraddeen +4 more
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Yuanzineng kexue jishuAfter Fukushima nuclear accident, the passive concept is widely adopted in the thermal safety design of advanced nuclear reactors. The in-pool passive residual heat removal system (PRHRS) can also provide security guarantee for the domestic reactor ...
LIAN Qiang1, 2, 3, ZHU Longxiang1, 2, 3, TANG Simiao1, 2, 3, HUANG Tao4, ZHANG Yong4, PAN Liangming1, 2
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Programmers Manual for the PVM Coupling Interface in RELAP5-3D
, 2005 This report describes the implementation of the PVM API in the RELAP5-3D© computer code. The information in the report is intended for programmers wanting to correct or extend RELAP5-3D©
Weaver, Walter L., III
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RELAP5/MOD3 code manual. Volume 4, Models and correlations [PDF]
, 1995 The RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents ...
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