2016
DOI: 10.1016/j.ijhydene.2016.01.157
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HTR steady state and transient thermal analyses

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Cited by 15 publications
(8 citation statements)
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“…One particular code owned by BATAN is the RELAP5/SCDAP/Mod3.4, which is originally developed for the thermal hydraulic transient simulation of light water reactor coolant systems. The use of RELAP5 to simulate the PBR, especially in the core, can be found in the thermal modelling of HTR-10 design [6,7]. The purpose of this research is to present preliminary results in the core temperature distribution in the EPR using the RELAP5/SCDAP/Mod3.4 to confirm its design parameter with the EPR basic design.…”
Section: Introductionmentioning
confidence: 99%
“…One particular code owned by BATAN is the RELAP5/SCDAP/Mod3.4, which is originally developed for the thermal hydraulic transient simulation of light water reactor coolant systems. The use of RELAP5 to simulate the PBR, especially in the core, can be found in the thermal modelling of HTR-10 design [6,7]. The purpose of this research is to present preliminary results in the core temperature distribution in the EPR using the RELAP5/SCDAP/Mod3.4 to confirm its design parameter with the EPR basic design.…”
Section: Introductionmentioning
confidence: 99%
“…As a non-condensable gas, helium in the gas cooled reactor is also accomodated in RELAP5 code. Application of RELAP5 in the gas cooled reactor can be found in the thermal modeling of HTR-10, which is focused only on the core section [6]. The present model of EPR is not only limited to the core section but also extended to the helium flows inside the reactor internal structures, especially inside the reflector.…”
Section: Modeling Of Epr Using Relap5 Codementioning
confidence: 99%
“…One particular code owned by BATAN is the RELAP5/SCDAP/Mod3.4, which is originally developed for the thermal hydraulic transient simulation of light water reactor coolant systems. The use of RELAP5 with other version and other similar code in modeling the PBR can be found in the research article related to the thermal modeling of HTR-10 design [6,7]. The purposes of this research is to develop a model of the EPR design using the RELAP5/SCDAP/Mod3.4 in order to study the RELAP5 capability in determining the most representative model for further safety analysis.…”
Section: Introduction *mentioning
confidence: 99%
“…Antioxidation coatings for carbon materials have been widely researched in the past years and show great feasibility without changing carbon materials’ excellent properties. According to HTGR reactor designs, temperature of the nuclear core can be up to 1673 K in common conditions or 1873 K in accident conditions and materials used in the reactors need to withstand the extreme environment for extended periods of time and remain structurally intact and retain fission products . Silicon carbide (SiC), one of the most promising ceramics, has been researched in the nuclear applications such as the TRISO coating in HTGR, the fuel design of gas‐cooled fast reactor and molten salt reactor, and so on, which has been already used or experimental verification successfully .…”
Section: Introductionmentioning
confidence: 99%