Results 51 to 60 of about 5,558 (186)
Simulation of Spray Injection in the Pressurizer Using RELAP5 [PDF]
, 2017 A modeling research using Relap5 to assess the pressurizer of a pressurized water reactor(PWR) power plant has been performed. The heater and water injection systems in the pressurizer system of the PWRare of greatimportance for system pressure control ...
Dibyo, S. (S), Susyadi, S. (S)
core +1 more source
Assessment of ECCMIX component in RELAP5 based on ECCS experiment
Nuclear Engineering and Technology, 2020 ECCMIX component was introduced in RELAP5/MOD3 for calculating the interfacial condensation. Compared to other existing components in RELAP5, user experience of ECCMIX component is restricted to developmental assessment applications.
Gongle Song +5 more
doaj +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
RELAP5-3D thermal hydraulic analysis of the target cooling system in the SPES experimental facility [PDF]
, 2014 The SPES (Selective Production of Exotic Species) experimental facility, under construction at the Italian National Institute of Nuclear Physics (INFN) Laboratories of Legnaro, Italy, is a second generation Isotope Separation On Line (ISOL) plant for ...
Buffa, P. +4 more
core +1 more source
RELAP5 Calculations of Bethsy 9.1b Test
Science and Technology of Nuclear Installations, 2012 Recently, several advanced computational tools for simulating reactor system behavior during real and hypothetical transient scenarios were developed.
Andrej Prošek
doaj +1 more source
Development and analysis of passive residual heat-removal system on secondary side of small reactor
He jishuBackgroundPassive residual heat-removal system (PRHRS) based on natural circulation has been widely used in small reactors connected on secondary side loop.PurposeThis study aims to develop and analyze a passive residual heat-removal system on the ...
DONG Botong +7 more
doaj +1 more source
He jishu, 2021 BackgroundThe liquid-fueled molten salt reactor (MSR) is one of the Generation IV advanced reactor concepts, which has unique advantages in aspects of safety, economy and nonproliferation.
LI Rui, CHENG Maosong, DAI Zhimin
doaj +1 more source
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
Development of M5 Cladding Material Correlations in the TRANSURANUS Code: Revision 1 [PDF]
, 2016 The technical report is based on an earlier research on material properties of the M5 structural material. Complementing this research with new M5 data found in open literature, a set of correlations has been developed for the implementation to the ...
HOLMSTROM BJORN +3 more
core +1 more source
Alexandria Engineering Journal, 2018 Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar +3 more
doaj +1 more source