Results 61 to 70 of about 362 (143)
Science and Technology of Nuclear Installations, 2010 The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
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Nuclear Engineering and Technology, 2018 An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with ...
Takeshi Takeda
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Core Flow Distribution from Coupled Supercritical Water Reactor Analysis
Science and Technology of Nuclear Installations, 2014 This paper introduces an extended code package PARCS/RELAP5 to analyze steady state of SCWR US reference design. An 8 × 8 quarter core model in PARCS and a reactor core model in RELAP5 are used to study the core flow distribution under various steady ...
Po Hu, Paul P. H. Wilson
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Uncertainty Analysis of RELAP5-3D© [PDF]
, 2012 As world-wide energy consumption continues to increase, so does the demand for the use of alternative energy sources, such as Nuclear Energy. Nuclear Power Plants currently supply over 370 gigawatts of electricity, and more than 60 new nuclear reactors have been commissioned by 15 different countries.
Gertman, Alexandra E +1 more
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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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Design basis accident analysis of a small modular reactor
Journal of Thermal Engineering, 2017 The International Reactor Innovative and Secure (IRIS) is an integrated small modular reactor (SMR) designed by Westinghouse Electric Company and a consortium of organizations.
Jivan Khatry, Fatih Aydogan
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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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RELAP5-3D Code Validation for RBMK Phenomena [PDF]
, 1999 The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a ...
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Science and Technology of Nuclear Installations, 2015 RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow regime maps, there is a concern that RELAP5 may provide significant errors for rapid transient ...
Viet-Anh Phung +3 more
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