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Journal Articles

Recent progress in the energy recovery linac project in Japan

Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05

Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.

Journal Articles

Progress in R&D efforts on the energy recovery linac in Japan

Sakanaka, Shogo*; Ago, Tomonori*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; Harada, Kentaro*; Hiramatsu, Shigenori*; Honda, Toru*; et al.

Proceedings of 11th European Particle Accelerator Conference (EPAC '08) (CD-ROM), p.205 - 207, 2008/06

Future synchrotron light sources based on the energy-recovery linacs (ERLs) are expected to be capable of producing super-brilliant and/or ultra-short pulses of synchrotron radiation. Our Japanese collaboration team is making efforts for realizing an ERL-based hard X-ray source. We report recent progress in our R&D efforts.

JAEA Reports

Use results of MOX fuel in ATR Fugen nuclear power station

Ijima, Takashi; ; Matsumoto, Mitsuo; *

JNC-TN3410 2000-002, 93 Pages, 2000/01

JNC-TN3410-2000-002.pdf:2.54MB

Fugen Nuclear Power Station ("Fugen") is a prototype Advanced Thermal Reactor (ATR), it has been demonstrated the plutonium utilization by loading many Mixed Oxide Fuels (MOX) since the reactor start up March 1979, and no fuel defect had been occurred, The MOX fuel assemblies has the high reliability and has been loaded more than 700 fuel assemblies. This is the largest in the world as a thermal neutron reactor. However, "Fugen" is planning to stop its operation in the year 2003, because the role of the Fugen almost finished. Therefore, we are going to summarize the ATR project including the Plutonium utilization experience. This paper is summarized as part of the experience.

JAEA Reports

None

Matsumoto, Mitsuo; ;

PNC-TN1410 98-005, 96 Pages, 1998/03

PNC-TN1410-98-005.pdf:2.17MB

no abstracts in English

JAEA Reports

None

; Matsumoto, Mitsuo;

PNC-TN1410 97-039, 99 Pages, 1997/10

PNC-TN1410-97-039.pdf:2.25MB

no abstracts in English

Journal Articles

MOX fuel design for thermal reactor

Matsumoto, Mitsuo

KURRI-TR-385, (385), p.33 - 46, 1994/02

None

Journal Articles

Recent Results of PIE on Fuel for Demonstration ATR

; ; Matsumoto, Mitsuo

ANP '92, 19-1 Pages, 1992/10

JAEA Reports

Computer code (DIRAD) for fuel temperature evaluation of LMFBR at early burnup

; *; ; ; ; Matsumoto, Mitsuo

PNC-TN8410 92-187, 21 Pages, 1992/05

PNC-TN8410-92-187.pdf:0.22MB

Computer code for fuel temperature evaluation of LMFBR at early burnup has been developed. On fule temperature evaluation, especially at early burnup, the fuel restructuring model and the gap conductance medel are important. These models which are installed in the temperature evaluation code, were verified based on the results of irradiation tests using the foreign fast reactor and "JOYO". This paper describes the essential parts of the models and the functions of the code (DIRAD) which is used for the fuel temperature evaluation at early burnup of LMFBR such as the prototype fast breeder reactor "MONJU".

Journal Articles

None

; ; ; Matsumoto, Mitsuo

ANP 92 INTERNATIONAL CONFTY OF ADVANCED NUCLEAR P, 2, 19-1 Pages, 1992/00

None

Journal Articles

Simplified model for the analysis on the duct wall deflection due to in-reactor creep in LMFBR fuel assemblies

Komoda, S.; Nakae, Nobuo; Matsumoto, Mitsuo

Journal of Nuclear Materials, 188, p.319 - 322, 1992/00

Journal Articles

Failure behavior of plutonium-uranium mixed oxide fuel under reactivity-initiated accident condition

Abe, Tomiyuki; Nakae, Nobuo; Kodato, Kazuo; Matsumoto, Mitsuo

Journal of Nuclear Materials, 188, p.154 - 161, 1992/00

JAEA Reports

Operation experience of MOX fuel loaded heavy water reactor

Shiratori, Yoshitake; Furubayashi, Toshiyuki; Matsumoto, Mitsuo

PNC-TN3410 91-031, 47 Pages, 1991/11

ugen has been operating safely and smoothly for twelve years using mainly plutonium-uranium mixed oxide (mox) fuels, and much operation data has been accumulated during this time. Fugen's core management has been established, and its core characteristics have been evaluated through the operation. the effect of $$^{241}$$am accumulation and plutonium composition ratio must be considered when many mox fuels are used in a thermal reactor. Calculation accuracy of core analysis code is good and core characteristics are well evaluated by the consideration of these factors. Fuel inspection shows that there is no big difference between mox and uo$$_{2}$$ fuel.

JAEA Reports

Long-life in-core neutron for prototype hoavy water reactor FUGEN

Oteru, Shigeru; Matsumoto, Mitsuo; Deshimau, Takehide; Tai, Ichio*; Hanai, Kohi*; Kameda, Akiyuki*

PNC-TN3410 88-015, 10 Pages, 1988/06

PNC-TN3410-88-015.pdf:0.32MB

A long-life in-core neutron detector was developed from 1973 through 1978 and since then, it has been applied to the prototype heavy water reactor "Fugen" as a local power monitor. More than 10 year's operation experience of the detector proved its performance as was expected. The detector is a fission chamber of regenerative type whose tube is made of zircaloy-2 metal for neutron economy. In-core neutron detectors for the local power monitor are placed in heavy water moderator of 50 c. The in-core conditions bring a high level thermal neutron flux environment. It tends to hurt the lineality and shorten the life time of the detectors because of rapid burnup of the neutron conversion material($$^{235}$$U)in thedetector compared to the light water reactors.These problems were solved by some improvements and it was demonstrated that the detector had the performance of high linearity and long-life characteristics.

JAEA Reports

Bellows for Control Rod Drive Mechanism of Monju

Matsumoto, Mitsuo; Ogawa T*; Ishii Y*; Yamagis*; Suzuki*

PNC-TN241 79-30VOL3, 18 Pages, 1979/09

PNC-TN241-79-30VOL3.pdf:0.53MB

The full mock-up operation test of Control Rod Drive Mechanism (CRDM) for "MONJU" have been carried on since 1972 in OEC of PNC. Welded type bellows were adopted for CRDM as the boundary between sodium and atmosphere. In design, two different locations were considered for bellows, one in sodium and the other in argon gas with sodium vapor and some experiences on the bellows have been obtained. Besides the prototype tests of CRDM, several R&D on CRDM bellows, such as environment effect test and endurance test are conducted.

JAEA Reports

The First loading fuel elements and power-up for JRR-2

JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1027, 57 Pages, 1962/09

JAERI-1027.pdf:4.76MB

no abstracts in English

JAEA Reports

Critical experiments and characteristic measurement for JRR-2

JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1025, 62 Pages, 1962/03

JAERI-1025.pdf:4.6MB

no abstracts in English

Journal Articles

None

; ; ; Matsumoto, Mitsuo;

Donen Giho, (86), 53-61 Pages, 

None

Journal Articles

None

Matsumoto, Mitsuo

Gekkan Denki Joho, (2), , 

None

Journal Articles

None

*; Matsumoto, Mitsuo; *

Nippon Genshiryoku Gakkai-Shi, 27(1), 48 Pages, 

Journal Articles

None

; ; ; Matsumoto, Mitsuo

Nippon Genshiryoku Gakkai-Shi, 29(5), 368 Pages, 

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

26 (Records 1-20 displayed on this page)