Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 2004.10a
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- Pages.131-132
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- 2004
Dosimetry Calculations for 3-D VENUS-2 MOX-Fuelled Reactor Using TRANSX/DANTSYS Code System
- Kim, Do-Heon (Korea Atomic Energy Research Institute) ;
- Gil, Choong-Sup (Korea Atomic Energy Research Institute) ;
- Chang, Jong-Hwa (Korea Atomic Energy Research Institute)
- Published : 2004.10.28
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