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Permana, S.; Suzuki, Mitsutoshi; Zaki, S.*
AIP Conference Proceedings 1448, p.119 - 125, 2012/06
Times Cited Count：0 Percentile：0.11(Nuclear Science & Technology)Nuclear fuel materials from spent fuel of light water reactors have a potential to be used for destructive devices with very huge energy release or in the same time, it can be utilized as a peaceful energy or civil applications, for generating electricity, desalination of water, medical application and others applications. Several research activities showed some recycled spent fuel can be used as additional fuel loading for increasing fuel breeding capability as well as improving intrinsic aspect of nuclear non-proliferation. The present investigation intends to evaluate the composition of heavy metals inventories and fuel breeding capability in the FBR design based on the loaded fuel of light water reactor (LWR) spent fuel (SF) based on the LWR SF composition of 33 GWd/t with 5 years cooling time by adopting depletion code of ORIGEN.
Permana, S.; Suzuki, Mitsutoshi; Suud, Z.*; Saito, Masaki*
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 7 Pages, 2011/12
Spent fuel (SF) of light water reactors (LWR) is loaded to increase breeding capability and intrinsic aspect of proliferation resistance. This present study intends to evaluate the effect of different loaded doping materials in the blanket region of FBR to the reactor performance and plutonium proliferation resistance level. Basic reactor operation is adjusted to reach 800 days operation by adopting 4 fuel batches systems of Japan Sodium Fast Reactor (JSFR) design. LWR plutonium compositions of Isotopic 
Pu and 
Pu show more sensitive to the decay time due to it shorter half-life which affect to the vector composition of plutonium as well as minor actinide (MA) as a function of decay time.
Permana, S.; Suzuki, Mitsutoshi; Saito, Masaki*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10
Trans-uranium (TRU) compositions of LWR and multi-cycle FBR have been loaded in the FBR design by adopting 4 fuel batches system. 800 days of cycle length was used to investigate the proliferation resistance of plutonium as well as core performance, during reactor operation. Different compositions of TRU as initial fuel composition affect to the fuel behavior, criticality condition and fuel breeding capability. It shows less excess reactivity and better fuel breeding for MA doping in the core. High decay heat (DH) and spontaneous fission neutron (SFN) compositions of plutonium which is mainly caused by high production of even mass of plutonium isotopes will be compared from both typical trans-uranium compositions of LWR and FBR.
Permana, S.; Suzuki, Mitsutoshi
Progress in Nuclear Energy, 53(7), p.958 - 963, 2011/09
Times Cited Count：6 Percentile：44.28(Nuclear Science & Technology)Material attractiveness evaluation based on isotopic plutonium barrier compositions have been investigated based on intrinsic feature of proliferation resistance such as decay heat (DH), spontaneous fission neutron (SFN), as well as attractiveness concepts of figure of merit (FOM) and attractiveness concept (ATTR) as a function of diluted fraction of even mass plutonium to Pu-239 composition.
Permana, S.; Suzuki, Mitsutoshi; Saito, Masaki*
Transactions of the American Nuclear Society, 104(1), p.714 - 715, 2011/06
Material attractiveness concepts for evaluating the level of proliferation resistance of nuclear fuel have been evolving and can be useful for determining general rules to assess the potential use of nuclear material for explosive devices. The two approaches examined here for evaluating material attractiveness are the attractiveness (ATTR) and figure of merit (FOM) concepts. Similar trend of material attractiveness level with ATTR and FOM is obtained by introducing MA doping in the blanket region and these loading MA is effective to reduce the material attractiveness level to practically unusable level of ATTR and low attractiveness level of FOM2.
Permana, S.; Suzuki, Mitsutoshi; Saito, Masaki
Journal of Nuclear Science and Technology, 48(5), p.724 - 733, 2011/05
Times Cited Count：10 Percentile：57.01(Nuclear Science & Technology)Fuel behaviors of the large fast breeder reactor have been investigated as well as material attractiveness based on isotopic plutonium composition for evaluating proliferation resistance aspect in regards to combine evaluation of decay heat and spontaneous fission neutron barrier as key parameters of isotopic material barrier. Trans-uranium fuel TRU in the core regions and doping MA in the blanket regions as the option of loading MA, produces higher Pu composition for denaturing plutonium which mainly comes from converted 
Np. Isotopic plutonium composition of TRU fuel has relatively less than its Pu composition of MOX fuel except for Pu composition which is obtained higher composition than MOX fuel. MA in the core or blanket regions which produces higher Pu composition becomes the key role for obtaining higher level material barrier of decay heat and spontaneous fission neutron compositions.
Permana, S.; Suzuki, Mitsutoshi; Kuno, Yusuke
Journal of Power and Energy Systems (Internet), 5(3), p.343 - 359, 2011/04
Material attractiveness analysis on isotopic plutonium composition of fast breeder reactors (FBR) has been investigated based on figure of merit (FOM) formulas as key parameters as well as decay heat (DH) and spontaneous fission neutron (SFN) compositions. Increasing minor actinide (MA) doping gives the significant effect to increase Pu composition; however, it composition of 
Pu and 
Pu become less. DH and SFN compositions in the core regions similar to the composition of MOX-grade and its DH and SFN compositions of blanket regions are categorized as compositions of weapon grade. Material attractiveness based on FOM1 formula shows all isotopic plutonium compositions in the blanket regions as well as in the core regions are categorized as high attractive material.
Permana, S.; Suzuki, Mitsutoshi; Saito, Masaki
Nuclear Engineering and Design, 241(1), p.101 - 117, 2011/01
Times Cited Count：11 Percentile：64.09(Nuclear Science & Technology)The effect of trans-uranium (TRU) fuel loading on the reactor core performance as well as the actinide and plutonium composition in the core and blanket regions has been analyzed based on the large FBR type. Isotopic plutonium composition of TRU fuel obtains less composition than that of MOX fuel except for Pu composition which obtains relatively higher composition. The significantly increasing composition is shown by Pu for TRU fuel in the core region as well as its increasing value in the blanket region for doping MA case. Excess reactivity can be reduced significantly and an additional breeding gain can be obtained by TRU fuel in comparison with MOX fuel. Doping MA in the blanket regions reduces the criticality for a small reduction value and it gives a reduction value of breeding ratio.
Permana, S.; Suzuki, Mitsutoshi
Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.515 - 520, 2010/10
Fast reactor technology becomes more important player to enhance the optimum fuel utilization as well as for minimizing spent fuel waste such as trans-uranium by adopting closed fuel cycle option. The embodied challenges for introducing closed fuel cycle are proliferation resistance (PR) aspect of nuclear fuel as well as utilizing advanced fuel reprocessing and fabrication facilities. High level of PR for future nuclear fuel cycles have to be considered which can be obtained from isotopic material barriers such as uranium isotopic barrier, neptunium, and plutonium and so on.
Permana, S.; Suzuki, Mitsutoshi
no journal, ,
Several concepts of material attractiveness have been investigated by adopting attractiveness (ATTR) and figure of merit (FOM) formula as well as decay heat (DH) and spontaneous fission neutron (SFN) compositions based on the composition of plutonium isotopes. These concepts will be applied to evaluate the material attractiveness level of core and blanket regions FBR design during reactor operation.
