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Rida SNM
Doctoral Student, Dept. Nuclear Engineering, Kyushu University, Japan
Astronomy Computer Science & IT Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering

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Feasibility Design Study of Long Life BWR with Natural Uranium/Thorium as Fuel Cycle Input Zaki Su'ud; Rijal Kurniadi; Rida SNM; Zuhair Zuhair
Indonesian Journal of Physics Vol 20 No 1 (2009): Vol. 20 No. 1, January 2009
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (95.554 KB) | DOI: 10.5614/itb.ijp.2009.20.1.4

Abstract

Feasibility design study of Long Life BWR with natural uranium/thorium as fuel cycle input has been performed. The reactor core is divided into 6 equal regions in radial direction. The fresh fuel is first loaded into the most outer region then shifted to the center of the core, and from there shifted to the nearby region in the outward direction. Nitride fuel is employed in the core to get better criticality and conversion/breeding ratio. The results show that uranium fuel combined with low moderating ratio environment is superior to make the system critical.
Fission Yield Calculation Method and its Effect in Nuclear Fuel Cell Homogenization Calculation Zaki Su’ud; M. Ali Shafii; Rida SNM
Indonesian Journal of Physics Vol 20 No 2 (2009): Vol. 20 No. 2, April 2009
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (100.463 KB) | DOI: 10.5614/itb.ijp.2009.20.2.3

Abstract

Zero burn-up core capability can eliminate possible super prompt critical accident and make possible of inherent safety feature based on reactivity feedback mechanism. In this concept the maximum excess reactivity is limited below 1 $ of reactivity so that possibility of super prompt accident such as in Chernobyl accident case can be eleminated. This is however need high quality of system analysis, and in this study the effect of fission yield calculation method on the nuclear fuel cell homogenization process is investigated and discussed. This study use SRAC code system to investigate the efect of reactor dependent fission yield distribution calculation. Calculation restults show that this process will has important improvement effect for long life high burnup core.
Co-Authors M. Ali Shafii Rijal Kurniadi Zaki Suud Zuhair Zuhair