Development of materials for a high temperature Gas cooled reactor in Korea

  • Park, Ji Yeon
  • Kim, Dae Whan
  • Kim, Dong Jin
  • Kim, Eoun Sun
  • Kim, Hong Pyo
  • 외 5명
Citations

SCOPUS

5

초록

The very high temperature reactor (VHTR) materials R&D started as an objective of the development of key technologies for a nuclear hydrogen production funded by the Korea government in 2006. We are performing materials R&D for 5 components: a reactor pressure vessel (RPV), a reactor/process intermediate heat exchanger (IHX) and hot gas duct, a control rods component, a reflector and support structures in the core region and reactor materials for the sulfur-iodine (SI) process. The scopes of our works are focused on a material screening/selection and qualification, codifications of a high temperature structural design to a very high temperature region, and to support the licensing of a system design, material characterizations and database establishments. Current target materials are modified 9Cr-lMo, alloy 617, graphite, ceramic fiber reinforced composite, Fe-Si and SiC.

키워드

Core regionHigh temperatureHigh temperature gas cooled reactorHot gasIntermediate heat exchangerKey technologiesMaterial characterizationsNuclear hydrogen productionReactor materialsReactor Pressure VesselSulfur-iodine processSupport structuresSystem designTarget materialsVery high temperature reactorsCeramic fibersChromiumControl rodsFiber reinforced materialsGas cooled reactorsGraphiteHigh temperature reactorsHydrogen productionIodinePressure vesselsReconstruction (structural)Silicon alloysSilicon carbideStructural designSulfurMaterialsAlloyCeramicsChromiumFibersGraphiteHigh TemperatureHydrogenIodineMaterialsReactorsSiliconSilicon CarbideSulfur
제목
Development of materials for a high temperature Gas cooled reactor in Korea
저자
Park, Ji YeonKim, Dae WhanKim, Dong JinKim, Eoun SunKim, Hong PyoKim, Sung HoKim, Weon-JuKim, Woo GonRyu, Woo SeogKim, Young Do
DOI
10.1115/HTR2008-58149
발행일
2009-07
유형
Conference Paper
저널명
2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
2
페이지
43 ~ 47