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論文

Enhancement of proliferation resistance properties of commercial FBRs by material barriers

Meiliza, Y.; 大木 繁夫; 川島 克之; 大久保 努

Progress in Nuclear Energy, 70, p.270 - 278, 2014/01

 被引用回数:2 パーセンタイル:16.53(Nuclear Science & Technology)

The possibility to enhance proliferation resistance of discharged plutonium in the blanket of fast breeder reactor (FBR) has been investigated in terms of reactor core design aspects. It can be achieved by increasing the fraction of even-mass-number plutonium isotopes in the discharged plutonium. Although it can be achieved by a radial blanket-free core, it also decreases the breeding ratio. By loading the blanket with plutonium (Pu) or minor actinides (MAs) or Pu-MA combination, it is possible to reduce the attractiveness of discharged plutonium. However, the loading material in the blanket should be kept in balance with achievable core performances, fuel fabrication, and fuel handling, accordingly and hence the criteria needed to comply with. It is found that applying the attractiveness or FOM criteria that using the combination of even-mass-number plutonium isotopes need more material to be loaded than the one needed when applying Pellaud's or Kessler's proposal that using only solely isotope fraction of plutonium.

論文

Study on FBR core concepts to increase proliferation resistance of plutonium in LWR-FBR transition period

Meiliza, Y.; 大木 繁夫; 川島 克之; 大久保 努

Journal of Nuclear Science and Technology, 50(6), p.615 - 628, 2013/05

 被引用回数:1 パーセンタイル:10.75(Nuclear Science & Technology)

The possibility to enhance proliferation resistance of discharged plutonium in fast breeder reactor (FBR) has been investigated in terms of reactor core design aspects. The provisional target for proliferation resistance measures based on Saito's ATTR is defined. It is found that a few percent of plutonium loading and/or Am/Cm loading, which come from various types of spent fuel, might satisfy the provisional target with a minimum impact on the core neutronic performances. On Am/Cm loading core, decay heat constraints for fuel handling aspects are found to be important and should be considered in design. There is not significant change on the current developing scenarios for LWR-FBR transition period by applying the measures based on Saito's ATTR. It is found that applying Kimura's proposal, 15% $$^{238}$$Pu content requires about 7% MA loading fraction both in the core and the blanket, and it only can be applied at limited case. The period to consume minor actinides is shorter than to consume plutonium.

論文

Effect of minor actinides doping on plutonium produced in large-scale FBR blanket

Meiliza, Y.; 大木 繁夫; 大久保 努

Progress in Nuclear Energy, 53(7), p.964 - 968, 2011/09

 被引用回数:1 パーセンタイル:10.77(Nuclear Science & Technology)

Plutonium recycling in fast breeder reactors (FBRs) is important from the viewpoint of effective utilization of energy resources. Nuclear nonproliferation must be ensured through all the recycling process. Nuclear safeguards could be used as an extrinsic approach to prevent the diversion and misuse of nuclear material. Moreover, denaturing plutonium as an intrinsic approach is also considered to be effective to enhance the proliferation resistance of the system. As one of plutonium denaturing methods, the present study deals with the possibility of denaturing by MA transmutation in FBR blanket from the viewpoint of accumulating even-mass-number plutonium isotopes.

論文

Investigation to enhance nonproliferation characteristics of commercial FBRs by material barrier aspect

大木 繁夫; Meiliza, Y.; 川島 克之; 大久保 努

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.561 - 570, 2011/05

A possibility to enhance the nonproliferation characteristics of a commercial FBR is investigated in terms of reactor core design aspects, though the rigorous safeguards and the physical protection of nuclear materials essentially keep the nonproliferation at a high level. By means of loading the fertile blanket with plutonium (Pu) or minor actinide (MA), it is possible to reduce the proportion of fissile isotopes to total Pu and the attractiveness of the Pu produced in the blanket. Moreover, a radial blanket-free core is also possible. The merits and demerits of each method are described for the practical optimization of a core concept.

口頭

高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究,2; 「常陽」照射Uサンプルの分析,1

須藤 光雄; 小山 真一; 大林 弘; Meiliza, Y.*; 相楽 洋*; 齊藤 正樹*

no journal, , 

高い核拡散抵抗性を有する高速増殖炉ブランケット燃料開発を行うために、高速実験炉「常陽」で照射したUサンプル中のPuの生成・消滅挙動を実験により評価した。

口頭

高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究,6; 「常陽」照射Uサンプルの分析,2

大西 貴士; 須藤 光雄; 大林 弘; 小山 真一; 田中 健哉; Meiliza, Y.*; 山本 哲郎*; 相楽 洋*; 齊藤 正樹*

no journal, , 

高い核拡散抵抗性を有する高速増殖炉ブランケット燃料開発を行うために、高速実験炉「常陽」で照射したUサンプル中のPuの生成・消滅挙動を実験により評価した。

口頭

Enhancement of nonproliferation property of commercial FBRs by material barriers, 3; Analysis of nonproliferation measures and related quantities

Meiliza, Y.; 大木 繁夫; 川島 克之; 大久保 努

no journal, , 

The possibility of the addition of Pu and MA into the blanket of fast breeder reactor (FBR) is investigated as one of denaturing methods to enhance the proliferation resistance (PR) property of Pu by material barriers. The present paper deals with analysis of nonproliferation measures and other quantities related to fuel fabrication and transportation.

口頭

プルトニウムの核拡散抵抗性についての核データライブラリ依存性

Meiliza, Y.; 大木 繁夫; 川島 克之; 大久保 努

no journal, , 

Dependence of heavy metal burnup characteristics in the blanket of fast breeder reactor (FBR) on nuclear data libraries (NDLs) is investigated in terms of proliferation resistance properties of plutonium. The following NDLs are compared ADJ2000R (an adjusted library based on JENDL-3.2), JENDL-3.3 and JENDL-4.0 using plutonium loading or Am/Cm loading of core design approaches to enhance proliferation resistance as comparison to uranium oxide fuel. In addition, the dependence of core performances on the NDLs is also investigated. It reveals that among plutonium isotopes, Pu-238 had the largest difference for JENDL-4.0 and Pu-242 for JENDL-3.3 compared with ADJ2000R. The difference of isomeric ratio of Am-241 capture reaction has significant effect on proliferation resistance properties of plutonium for Am/Cm loading case.

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