UO2 and PuO2 utilization in high temperature engineering test reactor with helium coolant

Abdul Waris, Indarta K. Aji, Novitrian, Syeilendra Pramuditya, Zaki Su'Ud

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

High temperature engineering test reactor (HTTR) is one of high temperature gas cooled reactor (HTGR) types which has been developed by Japanese Atomic Energy Research Institute (JAERI). The HTTR is a graphite moderator, helium gas coolant, 30 MW thermal output and 950 °C outlet coolant temperature for high temperature test operation. Original HTTR uses UO2 fuel. In this study, we have evaluated the use of UO2 and PuO2 in form of mixed oxide (MOX) fuel in HTTR. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. The result shows that HTTR can obtain its criticality condition if the enrichment of 235U in loaded fuel is 18.0% or above.

Original languageEnglish
Title of host publication4th International Conference on Theoretical and Applied Physics, ICTAP 2014
EditorsNi Nyoman Rupiasih, Wayan Gede Suharta, Hery Suyanto
PublisherAmerican Institute of Physics Inc.
ISBN (Electronic)9780735413665
DOIs
Publication statusPublished - Mar 11 2016
Externally publishedYes
Event4th International Conference on Theoretical and Applied Physics, ICTAP 2014 - Bali, Indonesia
Duration: Oct 16 2014Oct 17 2014

Publication series

NameAIP Conference Proceedings
Volume1719
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616

Conference

Conference4th International Conference on Theoretical and Applied Physics, ICTAP 2014
CountryIndonesia
CityBali
Period10/16/1410/17/14

All Science Journal Classification (ASJC) codes

  • Physics and Astronomy(all)

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