No secondary waste recycle technology for rare metals using the hydrophilic extraction with phase transfer phenomena

Tsukahara, Takehiko*; Saga, Kaname*; Suzuki, Hideya*; Matsumura, Tatsuro

Kurin Tekunoroji, 29(12), p.4 - 7, 2019/12

no abstracts in English

A Code for predicting the migration of ground additionals: MOGRA

Amano, Hikaru; Takahashi, Tomoyuki*

Genshiryoku eye, 48(6), p.69 - 73, 2002/06

http://ci.nii.ac.jp/naid/40005192351

no abstracts in English

Instruments for the measurement of stable elements mass ratios and their application to environmental samples for the analysis of environmental behaviour of global warming gases and environmentally additional materials

Amano, Hikaru; Porntepkasemsan, B.; Atarashi-Andoh, Mariko; Kushita, Kohei

KURRI-KR-53, p.6 - 9, 2000/09

no abstracts in English

None

*

JNC TN1440 2000-007, 115 Pages, 2000/08

JNC-TN1440-2000-007.pdf:4.45MB

no abstracts in English

MA transmutation in various fast reactor core concepts

Oki, Shigeo; Iwai, Takehiko*; Jin, Tomoyuki*

JNC TN9400 2000-080, 532 Pages, 2000/03

JNC-TN9400-2000-080.pdf:14.98MB

Transmutation Property of minor actinide nuclides (MA) was analyzed for fast reactor cores having different coolant and fuel types in order to obtain basic data for evaluating an ability of the efficient use of resource and reducing the effect on the environment. The investigated fast reactor cores were (a) sodium cooled and oxide fueled core, (b) lead cooled and nitride fueled core (BREST-300), (c) carbon dioxide gas cooled and oxide fueled core (ETGBR), (d)lead cooled and oxide fueled core, (e) sodium cooled and nitride fueled core (both He-bond and sodium-bond), and (f) sodium cooled and metallic fueled core. Followings were observed for the relation between MA transmutation property and the different types of coolant and fuel of fast reactor core. (1) For the MA transmutation rate, the relation "Oxide Metal Nitride" was found out for difference of fuel type. A main reason of the increment of MA transmutation rate is that the neutron flux level rises on nitride and metallic fueled cores in comparison with oxide core. (2) The relation "Lead Sodium and Carbon dioxide" can be seen for the MA transmutation rate in the difference of coolant, but it is not clear whether the cause is driven from the difference of coolant itself on the difference of core design. (3) The changes of MA transmutation property mentioned above are comparatively small.

Report of researchers' meeting on advanced nuclear fuel recycle system; Nuclear fuel recycle system and technology to be aimed and its research & development

; Moro, Satoshi; ; Kakehi, Isao; ;

PNC TN9410 98-033, 284 Pages, 1998/03

PNC-TN9410-98-033.pdf:9.34MB

System engineering division of OEC has being carried out a design study of the advanced nuclear fuel recycle system using electro-metallurgical process, aiming for improvements in safety, reliability, economy and a1so in environmental burden and nuclear non-proliferation. But the public criticism against nuclear power is more severe recently, and the situation is changing as seeing in the conclusion of the round-table conference on FBR. The researcher's meetings, in which researchers in PNC and from other organizations attended, were held during December, 1997 and March, 1998 in order to discuss on the advanced nuclear fuel recycle system and technology for FBR to be aimed in the future, and how to execute its research & development, etc. The conclusions of this meeting are as follows: (1)The future advanced FBR fuel cycle system shall be the system which has high potential for maximum utilization of uranium resources, and also for revolutionary improvements of economy, safety, environmental burden, etc. so as to be accepted in the society. (2)Regarding to the process of the future fuel eycle system, electro-metallurgical process that is able to apply for reprocessing of different types of fuel (oxide, metal and nitride) and is flexible for technical progress is recommended. Research & development of this system and technology shall be carried out. (3)The mission of PNC (new organization) is to select the most appropriate advanced FBR fuel cycle system from the viewpoint of the long-term FBR age in the future, and to conduct development of its system. It is expected for the new organization to execute its research and development steadily in cooperation with other research institutes, etc. under the nation-wide assessment and agreement. According to the above conclusions, the system engineering division will enhance the design study of the advanced FBR fuel cycle system and establish the definite concept of the system in cooperation with concerned in and ...

Realization development of the flexible waste management system for MA P&T technology, 17; Design of the HLW granulation equipment

Kawaguchi, Koichi; Segawa, Tomoomi; Ishii, Katsunori; Suzuki, Akihiro*

no journal, , 

no abstracts in English

Realization development of the flexible waste management system for MA P&T technology, 24-2; Design of the HLW granulation equipment

Kawaguchi, Koichi; Segawa, Tomoomi; Ishii, Katsunori; Suzuki, Akihiro*

no journal, , 

no abstracts in English

Study on advanced nuclear energy system based on the environmental impact of radioactive waste disposal, 1; Environmental load and nuclear fuel cycle conditions in waste disposal

Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*; Han, C. Y.*; Nakase, Masahiko*; Matsumura, Tatsuro; Chiba, Go*; Sagara, Hiroshi*; Takeshita, Kenji*

no journal, , 

no abstracts in English

Realization development of the flexible waste management system for MA P&T technology, 38; Conceptual design of the HLW dissolution for MA separation

Matsumura, Tatsuro; Suzuki, Akihiro*

no journal, , 

no abstracts in English