Results 41 to 50 of about 2,651,698 (166)
RBMK thermohydraulic safety assessments using RELAP5/MOD3 codes [PDF]
, 1995 The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These
Tsiklauri, G.V., Schmitt, B.E.
openaire +2 more sources
Advanced Presentation of BETHSY 6.2TC Test Results Calculated by RELAP5 and TRACE
Science and Technology of Nuclear Installations, 2012 Today most software applications come with a graphical user interface, including U.S. Nuclear Regulatory Commission TRAC/RELAP Advanced Computational Engine (TRACE) best-estimate reactor system code.
Andrej Prošek, Ovidiu-Adrian Berar
doaj +1 more source
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 ...
openaire +4 more sources
Application of RELAP5/Mod3.3 – Fluent coupling codes to CIRCE-HERO
Journal of Physics: Conference Series, 2019 Abstract This paper presents the work ongoing at the DICI (Dipartimento di Ingegneria Civile e Industriale) of the University of Pisa on the application of coupled methodology between Fluent CFD code and RELAP5/Mod3.3 system code. In particular, this methodology was applied to the LBE-water heat exchanger HERO, with the aim to analyse ...
Forgione N. +6 more
openaire +2 more sources
Heat Transfer Boundary Conditions in the RELAP5-3D Code [PDF]
Volume 3: Thermal Hydraulics; Instrumentation and Controls, 2008 The heat transfer boundary conditions used in the RELAP5-3D computer program have evolved over the years. Currently, RELAP5-3D has the following options for the heat transfer boundary conditions: (a) heat transfer correlation package option, (b) non-convective option (from radiation/conduction enclosure model or symmetry/insulated conditions), and (c ...
Riemke, Richard A. +2 more
openaire +1 more source
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
doaj +1 more source
Frontiers in Energy Research, 2021 In nuclear reactor system research, the multiscale coupled thermal-hydraulic (T-H) system code and CFD code is one of the most prevalent research areas, and it could help improve simulation fidelity and optimize nuclear reactor design.
Lin Sun +4 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
He jishu, 2023 BackgroundThe propagation of pressure waves in nuclear energy systems will cause hydraulic load effects, and it is particularly important for the analysis of structural loads to accurately simulate the propagation process of pressure waves.
GONG Zhengyu +4 more
doaj +1 more source
Transient analysis of SIRIO using RELAP5/MOD3.3 system code
Journal of Physics: Conference Series, 2023 Abstract The main outcome of the present paper is the feasibility analysis of SIRIO (Sistema di rimozione della Potenza di decadimento per Reattori InnOvativi) facility with conditions based on those of its reference facility. The aim of SIRIO project is to study an innovative Decay Heat Removal System (DHRS) for liquid metal reactor and
Martina Molinari +4 more
openaire +3 more sources