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Oguri, Hidetomo; Hasegawa, Kazuo; Ito, Takashi; Chishiro, Etsuji; Hirano, Koichiro; Morishita, Takatoshi; Shinozaki, Shinichi; Ao, Hiroyuki; Okoshi, Kiyonori; Kondo, Yasuhiro; et al.
Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.389 - 393, 2014/10
no abstracts in English
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.
Kato, Yoshiaki; Yamamoto, Toshio; Takada, Fumiki; Omi, Masao; Nakagawa, Tetsuya
JAEA-Testing 2008-004, 22 Pages, 2008/06
JAEA-Testing-2008-004.pdf:5.88MB
This report is concerned with replacement of the radiation monitors in the lead cells of JMTR Hot Laboratory in the 2007 fiscal year. It was carried out on two of seven systems of the radiation monitors. The designing, producing, installing, adjusting and inspecting were described.
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.
Se(
,
)
Se reactionsNakamura, Shoji; Furutaka, Kazuyoshi; Harada, Hideo; Kato, Toshio*
Journal of Nuclear Science and Technology, 45(2), p.116 - 122, 2008/02
Times Cited Count：6 Percentile：34.00(Nuclear Science & Technology)Thermal-neutron capture cross-sections (
) and resonance integrals (
) leading to ground and isomeric states of 
Se were measured by the activation method. Samples of high purity (99.99%) selenium oxide were irradiated in a rotary specimen rack at the research reactor of Rikkyo University. The irradiation of a cadmium-shielded sample was also conducted to obtain . Wires of Co/Al and Au/Al alloys, which have different sensitivities to neutrons in thermal and epithermal energy regions, were irradiated to monitor thermal neutron fluxes and epithermal components at the same position of one of the rack. A high purity Ge detector was used to measure the rays emitted from the irradiated samples and wires, and reaction rates were calculated from -ray yields. On the basis of Westcott's convention, the cross-sections were obtained as follows: 
= 0.057
0.003 b and 
=0.186 0.014 b leading to 
Se, 
= 0.536 0.046 b and = 0.867 0.102 b leading to 
Se.
Wakai, Eiichi; Ando, Masami; Sawai, Tomotsugu; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Stroller, R. E.*; Yamamoto, Toshio; Kato, Yoshiaki; Takada, Fumiki
Journal of Nuclear Materials, 367-370(1), p.74 - 80, 2007/08
Times Cited Count：10 Percentile：57.01(Materials Science, Multidisciplinary)no abstracts in English
Higuchi, Hidekazu; Osugi, Takeshi; Nakashio, Nobuyuki; Momma, Toshiyuki; Tohei, Toshio; Ishikawa, Joji; Iseda, Hirokatsu; Mitsuda, Motoyuki; Ishihara, Keisuke; Sudo, Tomoyuki; et al.
JAEA-Technology 2007-038, 189 Pages, 2007/07
JAEA-Technology-2007-038-01.pdf:15.13MBJAEA-Technology-2007-038-02.pdf:38.95MBJAEA-Technology-2007-038-03.pdf:48.42MBJAEA-Technology-2007-038-04.pdf:20.53MBJAEA-Technology-2007-038-05.pdf:10.44MB
The Advanced Volume Reduction Facilities (AVRF) is constructed to manufacture the waste packages of radioactive waste for disposal in the Nuclear Science Research Institute of the Japan Atomic Energy Agency. The AVRF is constituted from two facilities. The one is the Waste Size Reduction and Storage Facility (WSRSF) which is for reducing waste size, sorting into each material and storing the waste package. The other is the Waste Volume Reduction Facility (WVRF) which is for manufacturing the waste package by volume reducing treatment and stabilizing treatment. WVRF has an induction melting furnace, a plasma melting furnace, an incinerator, and a super compactor for treatment. In this report, we summarized about the basic concept of constructing AVRF, the constitution of facilities, the specifications of machineries and the state of trial operation until March of 2006.
Miwa, Yukio; Kaji, Yoshiyuki; Tsukada, Takashi; Yamamoto, Toshio; Kato, Yoshiaki; Yonekawa, Minoru; Matsui, Yoshinori
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04
Radiation-induced stress relaxation (RISR) test under uniaxial loading condition for tensile type specimens was carried out for type 316L stainless steel (SS). The specimens were irradiated in the Japan Materials Testing Reactor at 561 K to three dose levels (0.1-3 dpa) under four displacement constrained condition (prestrain range; 0.06-0.75%) in order to apply residual stress. Radiation hardening behavior and IASCC susceptibility of the RISR-tested 316L SS were examined by slow strain rate testing (SSRT) in oxygenated high temperature water. It was concluded from the SSRT results that the RISR had little influence on the radiation hardening behavior and IASCC susceptibility in the 316L SS. In all specimens, the residual stress rapidly decreased with increasing dose, and the residual stress level after irradiation was much lower than the stress level to initiate IASCC.
Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.
Journal of Nuclear Science and Technology, 44(3), p.441 - 447, 2007/03
Times Cited Count：10 Percentile：57.01(Nuclear Science & Technology)The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m
and the volume reduction ratio is from 1.7 to 3.7. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005.
Takahashi, Toru; Kato, Shoichi; Nakagiri, Toshio; Aoto, Kazumi
Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(4), p.347 - 357, 2006/12
no abstracts in English
Nakagiri, Toshio; Kase, Takeshi; Kato, Shoichi; Aoto, Kazumi
JSME International Journal, Series B, 49(2), p.302 - 308, 2006/05
A new thermo-chemical and electrolytic hybrid hydrogen production system in lower temperature range is newly proposed by the Japan Atomic Energy Agency (JAEA) to realize the hydrogen production from water by using the heat generation of sodium cooled Fast Breader Reactor (FBR). The system is based on sulfuric acid (H
SO
) synthesis and decomposition process developed earlier (Westinghouse process), and sulfur trioxide (SO
) decomposition process is facilitated by electrolysis with ionic oxygen conductive solid electrolyte to reduce the operation temperature 200-300 
C lower than Westinghouse process. SO decomposition was confirmed experimentally, and theoretical thermal efficiency was evaluated. Furthermore, hydrogen production experiments to substantiate the whole process were performed. Stable hydrogen and oxygen production were observed in the experiments, and maximum duration of the experiments was about 5 hours.
TcFurutaka, Kazuyoshi; Harada, Hideo; Nakamura, Shoji; Kato, Toshio; Fujii, Toshiyuki*; Yamana, Hajimu*; Raman, S.*
Journal of Nuclear and Radiochemical Sciences, 6(3), p.283 - 286, 2005/12
Results of a series of study are presented to accurately determine cross section ofTc(n,gamma)
Tc reaction for thermal neutron. An activation method in which rays inRu are analyzed, as well as an analysis of ground-state transitions inTc are employed. To reduce uncertainties of the results in an activation method, an attempt was made to determine -ray emission probabilities accurately. Though accuracies of the results were improved, the uncertainties are still larger than the requested values. Possible improvements are suggested.
Higuchi, Hidekazu; Momma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10
The JAERI constructed the Advanced Volume Reduction Facilities(AVRF). The AVRF consists of the Waste Size Reduction and Storage Facilities(WSRSF) and the Waste Volume Reduction Facilities(WVRF). By operating the AVRF, it will be able to produce waste packages for final disposal and to reduce the amount of the low level solid wastes. Cutting installations for large wastes such as tanks in the WSRSF have been operating since June 1999. The wastes treated so far amount to 600 m and the volume reduction ratio is around 1/3. The waste volume reduction is carried out by a high-compaction process or melting processes in the WVRF. The metal wastes from research reactors are treated by the high-compaction process. The other wastes are treated by the melting processes that enable to estimate radioactivity levels easily by homogenization and get chemical and physical stability. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005.
C in JMTRWakai, Eiichi; Jitsukawa, Shiro; Tomita, Hideki*; Furuya, Kazuyuki; Sato, Michitaka*; Oka, Keiichiro*; Tanaka, Teruyuki*; Takada, Fumiki; Yamamoto, Toshio*; Kato, Yoshiaki; et al.
Journal of Nuclear Materials, 343(1-3), p.285 - 296, 2005/08
Times Cited Count：51 Percentile：94.04(Materials Science, Multidisciplinary)The dependence of helium production on radiation-hardening and -embrittlement has been examined in a reduced-activation martensitic F82H steel doped with 
B, 
B and B+B irradiated at 250C to 2.2 dpa. The total amounts of doping boron were about 60 massppm. The range of He concentration produced in the specimens was from about 5 to about 300 appm. Tensile and fracture toughness tests were performed after neutron irradiation. 50 MeV-He
irradiation was also performed to implant about 85 appm He atoms at 120C by AVF cyclotron to 0.03 dpa, and small punch testing was performed to obtain DBTT. Radiation-hardening of the neutron-irradiated specimens increased slightly with increasing He production. The 100 MPam
DBTT for the F82H+B, F82H+B+B, and F82H+B were 40, 110, and 155C, respectively. The shifts of DBTT due to He production were evaluated as about 70C by 150 appmHe and 115C by 300 appmHe. The DBTT shift in the small punch testing was evaluated as 50C.
Nishitani, Tomohiro; Nakanishi, Tsutomu*; Yamamoto, Masahiro*; Okumi, Shoji*; Furuta, Fumio*; Miyamoto, Masaharu*; Kuwahara, Makoto*; Yamamoto, Naoto*; Naniwa, Kenichi*; Watanabe, Osamu*; et al.
Journal of Applied Physics, 97(9), p.094907_1 - 094907_6, 2005/05
Times Cited Count：68 Percentile：87.61(Physics, Applied)no abstracts in English
Nakagiri, Toshio; Kase, Takeshi; Kato, Shoichi; Aoto, Kazumi
Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 7 Pages, 2005/05
A new thermochemical and electrolytic hybrid hydrogen production system for sodium cooled FBR has been proposed and developed by JNC. SO3 splitting experiments, theoretical evaluation of thermal efficiency and hydrogen production experiments to substantiate the whole process were performed. Maximum 5 hours stable hydrogen production was obserbed in the hydrogen production experiments.
Nakagiri, Toshio; Kase, Takeshi; Kato, Shoichi; Aoto, Kazumi; Takamori, Yuji*
JNC TN9400 2005-016, 27 Pages, 2005/04
JNC-TN9400-2005-016.pdf:1.37MB
To improve the energy efficiency of the thermo-chemical and electrolytic hybrid hydrogen production system, the techniques and electrolysis condition which reduced the voltage loss of sulfurous acid solution electrolysis were surveyed and discussued. As the result of the survey and discussion, a gas diffusion type anode was effective in a reduction of voltage loss, a cathode poisoning by sulfur and a omission of SO absorption part. A membrane electrode assembly type cathode was expected to reduce a voltage loss because of the minimum distance between membrane and electrode. In the point of voltage loss reduction, a stream type cell was proper to achieve a rapid reaction material supply. It was effective for experimental apparatus with capability in 1L/h hydrogen production to adopt these techniques, because a cell, which adopted these techniques, achieved a current density of more than 100mA/cm
.
Nakagiri, Toshio; Horikiri, Morito; Kato, Shoichi; Kase, Takeshi; Aoto, Kazumi; Takamori, Yuji*; Fukasaku, Hiroshi*
JNC TN9400 2004-056, 98 Pages, 2004/09
JNC-TN9400-2004-056.pdf:5.58MB
Hydrogen production demonstration experiments from water by the thermochemical and electrolytic hybrid hydrogen production process were performed. The feasibility of this hydrogen production process was demonstrated and technical problems to operate longer uration and to develop 1Nl/h-H2 production experimental apparatus were extracted. (1) Continuous and stable hydrogen and oxygen generation by the hybrid process was measured in the four full process experiments and maximum test duration was about five hours. The generation rate of hydrogen and oxygen calculated from measured current in four full process experiments were 4.03ml/h - 5.04ml/h and 2.07ml/h - 2.78ml/h, respectively. The total amounts of generated hydrogen and oxygen in the four experiments were 35.00ml and 20.99ml. (2) Severe material corrosion was not observed for gold plated stainless steel and S03 electrolysis cell (YSZ, Pt paste electrode) which used in sulfuric acid atmosphere at about 550 deg-C, and ionic oxygen conductivity of YSZ did not decrease in the experiments. Nevertheless, corrosion of the gold plated outlet piping of S03 electrolysis cell was observed, and the corrosion by condensed sulfuric acid as suspected. (3) Technical problems to operate the present experimental apparatus for 100 hours and to develop test apparatus to generate 1Nl/h hydrogen, were extracted.
Wakai, Eiichi; Matsukawa, Shingo; Yamamoto, Toshio*; Kato, Yoshiaki; Takada, Fumiki; Sugimoto, Masayoshi; Jitsukawa, Shiro
Materials Transactions, 45(8), p.2641 - 2643, 2004/08
Times Cited Count：6 Percentile：40.37(Materials Science, Multidisciplinary)no abstracts in English
Wakai, Eiichi; Taguchi, Tomitsugu; Yamamoto, Toshio*; Kato, Yoshiaki; Takada, Fumiki
Materials Transactions, 45(8), p.2638 - 2640, 2004/08
Times Cited Count：1 Percentile：12.20(Materials Science, Multidisciplinary)no abstracts in English
