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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.
Suda, Kazunori; Suzuki, Mitsutoshi; Mochiji, Toshiro
AIP Conference Proceedings 1448, p.16 - 21, 2012/06
Times Cited Count：0 Percentile：0.11(Nuclear Science & Technology)Japan, a non-nuclear weapons state, has established a commercial nuclear fuel cycle including LWRs, and now is developing a fast neutron reactor fuel cycle as part of the next generation nuclear energy system, with commercial operation targeted for 2050. Japan Atomic Energy Agency (JAEA) is the independent administrative agency for conducting comprehensive nuclear R&D in Japan after the merger of Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC). JAEA and its predecessors have extensive experience in R&D, facility operations, and safeguards development and implementation for new types of nuclear facilities for the peaceful use of nuclear energy. As the operator of various nuclear fuel cycle facilities and numerous nuclear materials, JAEA makes international contributions to strengthen nuclear non-proliferation. This paper provides an overview of JAEA's development of nuclear non-proliferation and safeguards technologies, including remote monitoring of nuclear facilities, environmental sample analysis methods and new efforts since the 2010 Nuclear Security Summit in Washington D.C.
Ohashi, Hirofumi; Sato, Hiroyuki; Tachibana, Yukio; Kunitomi, Kazuhiko; Ogawa, Masuro
AIP Conference Proceedings 1448, p.50 - 58, 2012/06
Times Cited Count：10 Percentile：94.11(Nuclear Science & Technology)As the challenge to ensure no harmful release of radioactive materials at the accidents by deterministic approach instead to satisfy the safety goal of the risk by probabilistic approach, new concept of advanced reactor, an inherently-safe high temperature gas-cooled reactor, is proposed based on the experience of the operation of the actual HTGR in Japan, HTTR, and the design of the commercial plant (GTHTR300), utilizing the inherent safety features of the HTGR (i.e., safety features based on physical phenomena). The safety design philosophy of the inherently-safe HTGR for the safety analysis of the radiological consequences is determined as the confinement of radioactive materials is assured by only inherent safety features without engineered safety features, AC power or prompt actions by plant personnel if the design extension conditions occur. The concept and future R&D items for the inherently-safe HTGR are described in this paper.
