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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.endPage 66 -
dc.citation.number 1-3 -
dc.citation.startPage 63 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 417 -
dc.contributor.author Lee, Dong Won -
dc.contributor.author Bae, Young Dug -
dc.contributor.author Kim, Suk Kwon -
dc.contributor.author Shin, Hee Yun -
dc.contributor.author Hong, Bong Guen -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-22T05:44:45Z -
dc.date.available 2023-12-22T05:44:45Z -
dc.date.created 2013-06-19 -
dc.date.issued 2011-10 -
dc.description.abstract In order for a Korean Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) to be tested in the International Thermonuclear Experimental Reactor (ITER), fabrication method for the TBM FW such as Hot Isostatic Pressing (HIP, 1050 degrees C, 100 MPa, 2 h) has been developed including post HIP heat treatment (PHHT, normalizing at 950 degrees C for 2 h and tempering at 750 degrees C for 2 h) with Ferritic Martensitic Steel (FMS). Several mock-ups were fabricated using the developed methods and one of them, three-channel mock-up, was used for performing a High Heat Flux (HHF) test to verify the joint integrity. Test conditions were determined using the commercial code, ANSYS-11, and the test was performed in the Korea Heat Load Test (KoHLT) facility, which was used a radiation heating with a graphite heater. The mock-up survived up to 1000 cycles under 1.0 MW/m(2) heat flux and there is no delamination or failure during the test. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.417, no.1-3, pp.63 - 66 -
dc.identifier.doi 10.1016/j.jnucmat.2010.12.166 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-80053616953 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/3429 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=80053616953 -
dc.identifier.wosid 000297383000014 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE BV -
dc.title High heat flux test with HIP-bonded Ferritic Martensitic Steel mock-up for the first wall of the KO HCML TBM -
dc.type Article -
dc.relation.journalWebOfScienceCategory Materials Science, Multidisciplinary; Nuclear Science & Technology -
dc.relation.journalResearchArea Materials Science; Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -

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