2011
DOI: 10.1016/j.pnucene.2011.05.005
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Development of high temperature gas-cooled reactor (HTGR) fuel in Japan

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Cited by 43 publications
(26 citation statements)
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“…Second, JAEA has also developed zirconium carbide (ZrC)-coated fuel particles in laboratory scale. They are assured to maintain their integrity at higher temperatures and burn-up conditions [18]. Third, Japan presented that VHTR is a principal candidate for the Generation IV reactor systems.…”
Section: Japan Atomic Energy Agency (Jaea)mentioning
confidence: 99%
“…Second, JAEA has also developed zirconium carbide (ZrC)-coated fuel particles in laboratory scale. They are assured to maintain their integrity at higher temperatures and burn-up conditions [18]. Third, Japan presented that VHTR is a principal candidate for the Generation IV reactor systems.…”
Section: Japan Atomic Energy Agency (Jaea)mentioning
confidence: 99%
“…Terdapat beberapa produk fisi penting yang dihasilkan dalam bahan bakar selama reaktor beroperasi, seperti 134 Cs, 137 Cs, 90 Sr, 131 I, 110m Ag, 85 Kr dan 133 Xe, 107 Pd [9,10]. Produk fisi tersebut diusahakan agar tetap terkungkung dalam bahan bakar dan tidak terlepas ke lingkungan selama reaktor beroperasi.…”
Section: Pendahuluanunclassified
“…The current GIF design consists of a helium-cooled reactor with graphite as a moderator, TRISO fuel and coolant outlet temperature above 900 [9]. The second is the result of the German program, which was later imported by the People's Republic of China and developed in the Republic of South Africa as the Pebble Bed Modular Reactor (PBMR).…”
Section: Very-high-temperature Reactor (Vhtr)mentioning
confidence: 99%