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JAEA Reports

Investigation of utilizing plutonium as mixed oxide fuel (6); Evaluation of burn-up characteristics of PWR fuels

*

JNC TJ9420 2002-008, 50 Pages, 2003/02

JNC-TJ9420-2002-008.pdf:3.0MB

Burn-up characteristics of PWR fuels have been investigated for scenario study of FBR introduction and the other studies on practical use of FBR. Nuclear compositions, radioactivity and thermal power of actinides and fission products in the spent fuels of present burn-up (49 GWd/t) and high burn-up (60 GWd/t) have been evaluated using the burn-up calculation code ORIGEN-2. This study was carried out as a part of JNC's feasibility study on commercialized FBR cycle system. Main conditions and results of this study are follows; (1)Evaluation code. :ORIGEN-2 (open code) (2)Fuel enrichment [Burn-up:49 GWd/t, UO$$_{2}$$ fuel(U235 enrichment):4.6 wt%, MOX fuel(Pu enrichment):5.9 Wt%] [Burn-up:60 GWd/t, UO$$_{2}$$ fuel(U235 enrichment):5.3 wt%, MOX fuel(Pu enrichment):7.2 wt%] (3)Evaluation items. Decay change in nuclear compositions, radioactivity and thermal power of actinides and fission products during 10000 years (0, 1, 2, 3, 4, 5, 6, 10, 50,100, 1000, 10000y after burn-up)

Journal Articles

APPLICABILITY OF THE 3D TRANSPORT CODE TORT THE SHIELDING ANALYSIS OF THE REACTOR CAVITY SHIELDING FLOOR IN THE PROTOTYPE FBR MONJU

; Usami, Isao; *

Proceedings of International Conference on the Physics of Reactors (PHYSOR 2000), 0 Pages, 2000/00

None

JAEA Reports

Investigation of utilizing plutonium as mixed oxide fuel(3)

*; *; Suzuki, Katsuo*

JNC TJ9440 99-014, 73 Pages, 1999/03

JNC-TJ9440-99-014.pdf:2.31MB

Planning of the plutonium utilization in a thermal reactor have been investigated to evaluate the scenario for FBR development. Plans for the partial loading of MOX fuel in the Takaham-3,4 plant are studied. Information of the full MOX utilizing plans in an advanced light water reactor is summarized based on the documents distributed at the related technical committee. Nuclear compositions of the spent MOX fuel have been evaluated using SRAC and ORIGEN-2 code. Results of the study are as follows: (1)Surveying the status of MOX fuel utilization. Based on the public documents, the status and plans for utilizing both the partial loading and the full loading of MOX fuel in the LWR core have been summarized. (2)Evaluation of spent MOX fuel compositions. Nuclear compositions of the spent MOX fuel have been evaluated and summarized for both the APWR uranium core and APWR plutonium core.

Journal Articles

Conceptual study of the lead-bismuth cooled accelerator-driven transmutation system

Tsujimoto, Kazufumi; Sasa, Toshinobu; Takizuka, Takakazu; Takano, Hideki; Mukaiyama, Takehiko; *; Kamishima, Y.*; *

Proc. of 2nd Int. Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98), p.137 - 143, 1998/00

no abstracts in English

Journal Articles

Intense proton accelerator development program

Mizumoto, Motoharu; ; *; *; Tanaka, Hideki*; Okumura, Yoshikazu; Kaneko, Yoshihiko

LA-12205-C, p.736 - 752, 1991/11

no abstracts in English

Journal Articles

Study on a drift tube linac for the basic technology accelerator in JAERI

*; Mizumoto, Motoharu; ; *; *; Kaneko, Yoshihiko

Proc. of the 16th LINEAR Accelerator Meeting in Japan, p.127 - 129, 1991/09

no abstracts in English

Journal Articles

A Study for high intensity proton linear accelerator development in JAERI

Mizumoto, Motoharu; ; *; *; Tanaka, Hideki*; Okumura, Yoshikazu; ; *; *; Kaneko, Yoshihiko

Proc. of the 16th LINEAR Accelerator Meeting in Japan, p.121 - 123, 1991/09

no abstracts in English

Journal Articles

Study on a radio frequency quadrupole for the basic technology accelerator in JAERI

; Mizumoto, Motoharu; *; *; Kaneko, Yoshihiko

Proc. of the 16th LINEAR Accelerator Meeting in Japan, p.124 - 126, 1991/09

no abstracts in English

JAEA Reports

Shilding Benchmark Problems

; ; *; *; Nakazawa, Masaharu*; *; *; *; ; *; et al.

JAERI-M 7843, 219 Pages, 1978/09

JAERI-M-7843.pdf:19.05MB

no abstracts in English

JAEA Reports

The Analysis of the Mozart expeimental data

Kobayashi, Takatoshi*; Yokobori, Hitoshi*; Sasaki, Makoto*; Tada, Keiko*

PNC TJ206 73-07, 228 Pages, 1973/04

PNC-TJ206-73-07.pdf:8.06MB

no abstracts in English

Oral presentation

Study of an epithermal neutron generator for BNCT using 400 MeV protons

Tahara, Yoshihisa*; Abe, Shinji*; Yonai, Shunsuke*; Baba, Mamoru*; Unno, Yasuhiro*; Sasa, Toshinobu; Iwanaga, Kohei; Yokobori, Hitoshi*; Tsutsui, Takehiko*; Kamei, Yoshihide*

no journal, , 

To realize the boron neutron capture therapy, the existence of the method using the 400 MeV proton beam, which is planned to supply the J-PARC transmutation experimental facility, are studied. As the preliminary examination, a method to obtain epithermal neutron using neutrons which generated by Ta target bonbarded by 400 MeV protons and moderated with iron and fluental moderators. To suppress the unexpected exposure, lead reflector is located around the target and moderators. By the preliminary analysis using MCNPX code and LA150 cross section library, the beam current about 5 micro ampere are enough for effective for brain-canther treatment.

Oral presentation

Study of the epithermal neutron source for BNCT by bombardment of 400MeV proton

Tahara, Yoshihisa*; Abe, Shinji*; Sasa, Toshinobu; Yonai, Shunsuke*; Baba, Mamoru*; Yokobori, Hitoshi*

no journal, , 

Conceptual study of the epithermal neutron source for BNCT by the bomberdment of 400 MeV proton which is planned to supply at Japan proton accelerator research complex, J-PARC. The neutron source, which has two neutron extraction port, is designed to obtain epithermal neutron source by the moderation of spallation neutron source from tungsten target using iron and fluental moderator. By the analytical result of the radiation dose in human phantom located at the exit of exposure port, about 60 minutes of irradiation time is obtained by the injection of 5 micro ampere protons. It is shown that this spallation neutron source is applicable to the epithermal neutron source for BNCT.

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