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Yamane, Ikumi; Takahashi, Nobuo; Sawayama, Kengo; Nishiwaki, Hiroki; Matsumoto, Takashi; Ogawa, Jumpei; Nomura, Mitsuo; Arima, Tatsumi*
JAEA-Technology 2021-038, 18 Pages, 2022/02
JAEA-Technology-2021-038.pdf:1.61MB
We have dismantled uranium enrichment facilities in Ningyo-toge Environmental Engineering Center since their operation finished in 2001, and the total amount of metallic wastes is estimated to be about 130 thousand tons. Eighty percent of them can be disposed as nonradioactive waste (NR), but there are some steel parts possibly uranium-contaminated. We need removing painted surface of such steels and radiologically surveying to dispose them as NRs. Though painted surfaces have been conventionally removed through hand working with grinders, this manual work requires installation of green house, protective clothing, and full-face mask, in order to prevent dispersion and inhalation of airborne dusts. We desire further developments of surface cleaning techniques to reduce time, cost, workload, and secondary waste generation caused by excessive grinding. Therefore, in this study, we focused on the laser cleaning technology used for the separation and removal of paint films at construction sites. In order to improve the coating separation and removal technology for NR objects, we evaluated the coating separation and removal performance of NR steel surface by laser cleaning system, observed the coating scattering behavior by high-speed camera and investigated the coating recovery method, evaluated the laser separation and removal performance of steel surface powder, and thermodynamically evaluated the uranium compounds on steel surface. We additionally evaluated the feasibility of laser cleaning techniques in our works basing on these results, and discussed future work plans for further developments of laser cleaning techniques.
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.
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.
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.
; Yamaguchi, Takashi; ; Matsumoto, Mitsuo
Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00
None
; ; ; ; Kobayashi, Tetsuro*; ; Sugawara, Satoru; Matsumoto, Mitsuo
Donen Giho, (94), p.36 - 52, 1995/06
None
; Abe, Tomiyuki; Matsumoto, Mitsuo
ANP '92, 19-1 Pages, 1992/10
; *; ; ; ; Matsumoto, Mitsuo
PNC TN8410 92-187, 21 Pages, 1992/05
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".
; ; ; Matsumoto, Mitsuo
ANP 92 INTERNATIONAL CONFTY OF ADVANCED NUCLEAR P, 2, 19-1 Pages, 1992/00
None
Komoda, S.; Nakae, Nobuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.319 - 322, 1992/00
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)Abe, Tomiyuki; Nakae, Nobuo; Kodato, Kazuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.154 - 161, 1992/00
Times Cited Count：6 Percentile：53.17(Materials Science, Multidisciplinary)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 
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
fuel.
Oteru, Shigeru; Matsumoto, Mitsuo; Deshimau, Takehide; Tai, Ichio*; Hanai, Kohi*; Kameda, Akiyuki*
PNC TN3410 88-015, 10 Pages, 1988/06
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(
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.
; ; ; Matsumoto, Mitsuo
Nihon Genshiryoku Gakkai-Shi, 29(5), p.368 - 384, 1987/05
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)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.
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
no abstracts in English
