Results 11 to 20 of about 1,033,988 (155)
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
doaj +2 more sources
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 ...
Fisher, J.E., Fisher, James Ebberly
openaire +5 more sources
Implementation of DOWTHERM A Properties into RELAP5-3D/ATHENA [PDF]
, 2010 DOWTHERM A oil is being considered for use as a heat transfer fluid in experiments to help in the design of heat transfer components for the Next Generation Nuclear Plant (NGNP). In conjection with the experiments RELAP5-3D/ATHENA will be used to help design and analyzed the data generated by the experiments. Inorder to use RELAP5-3D the thermophysical
Moore, Richard L.
openaire +3 more sources
RELAP5-3D Code Includes ATHENA Features and Models [PDF]
Volume 2: Thermal Hydraulics, 2006 Version 2.3 of the RELAP5-3D computer program includes all features and models previously available only in the ATHENA version of the code. These include the addition of new working fluids (i.e., ammonia, blood, carbon dioxide, glycerol, helium, hydrogen, lead-bismuth, lithium, lithium-lead, nitrogen, potassium, sodium, and sodium-potassium) and a ...
Riemke, Richard A. +2 more
openaire +2 more sources
Programmers Manual for the PVM Coupling Interface in RELAP5-3D [PDF]
, 2005 This report describes the implementation of the PVM API in the RELAP5-3D© computer code. The information in the report is intended for programmers wanting to correct or extend RELAP5-3D©.
Weaver, Walter L., III
openaire +3 more sources
RELAP5-3D Restart and Backup Verification Testing [PDF]
, 2013 Existing testing methodology for RELAP5-3D employs a set of test cases collected over two decades to test a variety of code features and run on a Linux or Windows platform. However, this set has numerous deficiencies in terms of code coverage, detail of comparison, running time, and testing fidelity of RELAP5-3D restart and backup capabilities.
Mesina, Dr. George L
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The Concept of the Heat Removal System of a High‐Flux Research Reactor
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 Achieving high neutron fluxes in research pressurized water reactors is directly related to the intensity of the coolant flow through the core and the pressure in it, which provides an increased saturation temperature and a margin to critical heat flux.
Vitaly Uzikov +3 more
wiley +1 more source
Development of an MPS Code for Corium Behavior Analysis: 3D Alloy Melting
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The moving particle semi‐implicit (MPS) method as a Lagrangian method is attracting increasing attention in severe accident analysis. In this paper, we developed an MPS code for the corium behavior analysis with several additional models added: an improved heat transfer model to improve the calculation between different materials, an enthalpy‐based ...
Lijun Jian +5 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The use of the USNRC codes TRACE and PARCS has been considered for the coupled safety analysis of CANDU reactors. A key element of CANDU simulations is the interactions between thermal‐hydraulic and physic phenomena with the CANDU reactor regulating system (RRS). To date, no or limited development has taken place in TRACE‐PARCS in this area.
Simon Younan +2 more
wiley +1 more source
Steady‐State Thermal‐Hydraulic Analysis of the LEU‐Fueled Dalat Nuclear Research Reactor
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 This paper presents results of steady‐state thermal‐hydraulic analysis for the designed working core of the Dalat Nuclear Research Reactor (DNRR) using the PLTEMP/ANL code. The core was designed to be loaded with 92 low‐enriched uranium (LEU) VVR‐M2 fuel bundles (FBs) and 12 beryllium rods surrounding a neutron trap at the core center, for replacement ...
Kien-Cuong Nguyen +5 more
wiley +1 more source