Results 21 to 30 of about 362 (143)
Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The rupturing of steam generator tubes leads to serious accidents in nuclear power plants. It causes radioactive materials to leak into the secondary system and release outside the reactor containment region. Therefore, it is important to model a technique to determine whether the natural circulation within a reactor coolant system (RCS) can cause ...
Dae Kyung Choi +6 more
wiley +1 more source
Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data
Nuclear Engineering and Technology, 2020 We validated the performance of RELAP MOD3.3 code regarding the hybrid SIT with available experimental data. The concept of the hybrid SIT is to connect the pressurizer to SIT to utilize the water inside SIT in the case of SBO or SB-LOCA combined with ...
Ho Joon Yoon +3 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2017 Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions.
Eltayeb Yousif +3 more
doaj +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
Brayton cycle numerical modeling using the RELAP5-3D code, version 4.3.4
Brazilian Journal of Radiation Sciences, 2019 This work contributes to enable and develop technologies to mount fast microreactors, to generate heat and electric energy, for the purpose to warm and to supply electrically spacecraft equipment and, also, the production of nuclear space propulsion ...
Eduardo Pedroso Longhini +4 more
doaj +1 more source
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
Transient analysis of OSU-MASLWR with RELAP5
Journal of Physics: Conference Series, 2022 Abstract The present paper deals with the assessment of the original and a modified version of RELAP5/MOD3.3 against the OSU Multi Application Small Light Water Reactor (OSU-MASLWR). The new implemented features regard suitable correlations for the heat transfer coefficient evaluation in helical geometry.
Molinari M. +3 more
openaire +1 more source
Uncertainty Analysis for RELAP5-3D [PDF]
, 2011 In its current state, RELAP5-3D is a 'best-estimate' code; it is one of our most reliable programs for modeling what occurs within reactor systems in transients from given initial conditions. This code, however, remains an estimator. A statistical analysis has been performed that begins to lay the foundation for a full uncertainty analysis.
Pawel, Aaron J., Mesina, Dr. George L.
openaire +2 more sources
RELAP5/MOD2 models and correlations [PDF]
, 1988 A review of the RELAP5/MOD2 computer code has been performed to assess the basis for the models and correlations comprising the code. The review has included verification of the original data base, including thermodynamic, thermal-hydraulic, and geothermal conditions; simplifying assumptions in implementation or application; and accuracy of ...
Dimenna, R. A. +7 more
openaire +2 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