Results 31 to 40 of about 5,521 (168)
Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code [PDF]
, 2016 This paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose.
Batet Miracle, Lluís +3 more
core +2 more sources
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility [PDF]
, 2019 CIRCE is a lead–bismuth eutectic alloy (LBE) pool facility aimed to simulate the primary system of a heavy liquid metal (HLM) cooled pool-type fast reactor.
Caruso G. +4 more
core +1 more source
Yuanzineng kexue jishu, 2023 Compared with traditional large scale pressurized water reactor, the volume of the containment of small pressurized water reactor is small. During a loss of coolant accident (LOCA), the containment pressure of small pressurized water reactor rises ...
QIN Bitan;ZHAO Dihong;HONG Gang;LU Jiaming;ZHANG Yaoli
doaj
Development and Verification of Visual Interactive Simulation Platform for Reactor System
Yuanzineng kexue jishu, 2023 RELAP5 is one of the most commonly used programs for reactor thermal hydraulic analysis. Due to the early developing time, RELAP5 does not have a friendly graphical user interface and interactive interface, resulting in the lack of human-computer ...
ZHANG Penghui;LU Guoqing;CHEN Ronghua;XU Wanqing;SU Guanghui;TIAN Wenxi;QIU Suizheng
doaj
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1989 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of ...
Allison, C. M. +13 more
openaire +6 more sources
He jishu, 2022 BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential.
SONG Shiyang +3 more
doaj +1 more source
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1990 This report describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various light water reactor (LWR) accident analysis computer programs. Formulation of the materials properties are generally semiempirical in nature.
Hohorst +5 more
openaire +2 more sources
Frontiers in Energy Research, 2022 Simulations of radiation heat transfer in fuel rod bundles are necessary for the thermal hydraulic design and safety analysis of open lattice gas-cooled reactors, which always operate at high temperatures.
Qian Sun, Yu Ji, Jun Sun
doaj +1 more source
Science and Technology of Nuclear Installations, 2015 In earlier study we have demonstrated that RELAP5 can predict flow instability parameters (flow rate, oscillation period, temperature, and pressure) in single channel tests in CIRCUS-IV facility. The main goals of this work are to (i) validate RELAP5 and
Viet-Anh Phung, Pavel Kudinov
doaj +1 more source
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
openaire +2 more sources