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Cu and 
Cu via the Zn(n, p)Cu and 
Zn(n, np/d)Cu reactions using accelerator neutronsKawabata, Masako*; Motoishi, Shoji*; Ota, Akio*; Motomura, Arata*; Saeki, Hideya*; Tsukada, Kazuaki; Hashimoto, Shintaro; Iwamoto, Nobuyuki; Nagai, Yasuki*; Hashimoto, Kazuyuki*
Journal of Radioanalytical and Nuclear Chemistry, 330(3), p.913 - 922, 2021/12
Times Cited Count：7 Percentile：72.21(Chemistry, Analytical)Both Cu and Cu are promising radionuclides in nuclear medicine. Production yields of these radionuclides were quantified by irradiating 55.4 g of natural zinc with accelerator neutrons. Clinically suitable Cu and Cu yields were estimated by experimental based numerical simulations using 100 g of enriched Zn and Zn, respectively, and elevated neutron fluxes from 40 MeV, 2 mA deuterons. A combined thermal- and resin-separation method was developed to isolate Cu and Cu from zinc, resulting in 73% separation efficiency and 97% zinc recovery. Such methods can provide large scale production of Cu and Cu for clinical applications.
Iwasa, Toma; Takano, Masahide
JAEA-Technology 2020-024, 29 Pages, 2021/03
JAEA-Technology-2020-024.pdf:2.33MB
Partitioning and transmutation of minor actinides (MA) is an important issue to reduce volume and radio-toxicity of high-level radioactive wastes. In Nuclear Science Research Institute, we have been carrying out R&D on MA-bearing nitride fuel for accelerator driven system. In the actual nitride fuel fabrication process, a special nitrogen gas highly enriched with 
N is required to avoid 
C production from N by (n,p) reaction in the fuel. For the economical use of such expensive gas, we need a nitrogen circulation refining system that can remove carbon monoxide (CO) evolved by carbothermic nitridation of oxides and can use the nitrogen gas in the closed system without loss. To develop the system, at first we listed up the performance requirements, and then designed and assembled a prototype system for laboratory-scale demonstration. The system consists of CO removal unit and circulation unit that can automatically keep the system pressure and the gas flow rate constant. As a result of demonstration on the nitridation of oxide, both units completely satisfy the requirements. We confirmed that the concept can be applied to the actual fuel fabrication with further additional function such as automatic hydrogen feed for the control of decarburization.
Haraga, Tomoko; Tsujimura, Hiroto*; Miyauchi, Saori*; Kamimura, Takuya*; Shibukawa, Masami*; Saito, Shingo*
Electrophoresis, 41(13-14), p.1152 - 1159, 2020/07
Times Cited Count：6 Percentile：45.07(Biochemical Research Methods)A novel combination of CE-based separation techniques was used for the precise fractionation of ionic compounds from impurities. The combination of on-capillary concentration and separation using transient isotachophoresis, with multiple injections and a two-point detection system provided higher efficiency, and accuracy at a microliter-scale injection volume, than when CE was individually used for purification. In this paper, we present successful applications of the CE fractionation techniques for the purification of fluorescein, fluorescein-4-isothiocyanate, two fluorescent metal ion probes, and a fluorescein-modified DNA aptamer. The purity of the isolated fluorescent probes ranged from 95 to 99%. The purified probe solutions were practical for use as purified stock solutions. The method developed was useful for the purification of anionic fluorescent reagents to be of ultratrace analytical grade for use with CE-LIF.
Tateno, Haruka; Sato, Takumi; Tsubata, Yasuhiro; Hayashi, Hirokazu
Journal of Nuclear Science and Technology, 57(3), p.224 - 235, 2020/03
Times Cited Count：6 Percentile：55.67(Nuclear Science & Technology)Fuel cycle technology for the transmutation of long-lived minor actinides (MAs) using an accelerator-driven system has been developed using the double-strata fuel cycle concept. A mononitride solid solution of MAs and Pu diluted with ZrN is a prime fuel candidate for the accelerator-driven transmutation of MAs. Pyro-reprocessing is suitable for recycling the residual MAs in irradiated nitride fuel with high radiation doses and decay heat. Spent nitride fuel is anodically dissolved, and the actinides are recovered simultaneously into a liquid cadmium cathode via molten salt electrorefining. The process should be designed to achieve the target recovery yield of MAs and the acceptable impurity level of rare earths in the recovered material. We evaluated the material balance during the pyro-reprocessing of spent nitride fuel to gain important insight on the design process. We examined the effects of changing processing conditions on material flow and quantity of waste.
Pu/
U ratios in individual particles by ICP-MS without prior chemical separationEsaka, Fumitaka; Suzuki, Daisuke; Miyamoto, Yutaka; Magara, Masaaki
Microchemical Journal, 118, p.69 - 72, 2015/01
Times Cited Count：8 Percentile：29.03(Chemistry, Analytical)The determination of the time elapsed since the last purification of plutonium with chemical separation gives important information for monitoring nuclear activities related to reprocessing and nuclear weapon production. Although methods for the analysis of plutonium solutions have been extensively studied, few studies were conducted for the measurement of individual particles. In this work, a simple technique was developed for age determination of individual plutonium particles by a combination of single particle dissolution and measurement by inductively coupled plasma mass spectrometry (ICP-MS) without prior chemical separation. The analytical results of individual plutonium particles having an age of 5.98 y indicated that the use of Pu/U ratios allowed for the determination of accurate ages, though that of 
Pu/
U and 
Pu/
U ratios was not suitable because of the contamination of natural uranium during the process of sample preparation.
Fukada, Satoshi*; Hayashi, Takumi
Nihon Genshiryoku Gakkai-Shi, 47(9), p.623 - 629, 2005/09
no abstracts in English
Shirai, Osamu*; Yamana, Hajimu*; Iwai, Takashi; Arai, Yasuo
Proceedings of Nuclear Fuel Cycle Technologies Closing the Fuel Cycle (CD-ROM), 7 Pages, 2003/00
no abstracts in English
Isobe, Kanetsugu; Imaizumi, Hideki*; Hayashi, Takumi; Konishi, Satoshi; Nishi, Masataka
Fusion Science and Technology, 41(3), p.988 - 992, 2002/05
no abstracts in English
Iizuka, Masatoshi*; Inoue, Tadashi*; Iwai, Takashi; Shirai, Osamu; Arai, Yasuo
Denryoku Chuo Kenkyusho Hokoku (T99078), 24 Pages, 2000/06
no abstracts in English
Kakehi, Isao; Tozawa, Katsuhiro; ; ; *
JNC TN9400 2000-053, 99 Pages, 2000/04
JNC-TN9400-2000-053.pdf:7.47MB
This report describes accomplishment of simulations of Pyrochemical Process Operation by using virtual engineering models. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. This system is a batch treatment system of reprocessing and re-fabrication, which transports products of solid form from a process to next process. As a result, this system needs automated transport system for process operations by robotics. ln this study, a simulation code system has been prepared, which provides virtual engineering environment to evaluate the pyrochemical process operation of a batch treatment system using handling robots. And the simulation study has been conducted to evaluate the required system functions, which are the function of handling robots, the interactions between robot and process equipment, and the time schedule of process, in the automated transport system by robotics. As a result of simulation of the process operation, which we have designed, the automated transport system by robotics of the pyrochemical process is realistic. And the issues for the system development have been pointed out.
Tozawa, Katsuhiro; ; Kakehi, Isao
JNC TN9400 2000-052, 110 Pages, 2000/04
JNC-TN9400-2000-052.pdf:4.39MB
This report describes accomplishment of development of a cathode processor calculation code to simulate the mass and heat transfer phenomena with the distillation process and development of an analytical model for cooling behavior of the pyrochemical process cell on personal computers. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. The cathode processor calculation code with distillation process was developed. A code validation calculation has been conducted on the basis of the benchmark problem for natural convection in a square cavity. Results by using the present code agreed well for the velocity-temperature fields, the maximum velocity and its location with the benchmark solution published in a paper. The functions have been added to advance the reality in simulation and to increase the efficiency in utilization. The test run has been conducted using the code with the above modification for an axisymmetric enclosed vessel simulating a cathode processor, and the capability of the distillation process simulation with the code has been confirmed. An analytical model for cooling behavior of the pyrochemical process cell was developed. The analytical model was selected by comparing benchmark analysis with detailed analysis on engineering workstation. Flow and temperature distributions were confirmed by the result of steady state analysis. In the result of transient cooling analysis, an initial transient peak of temperature occurred at balanced heat condition in the steady-state analysis. Final gas temperature distribution was dependent on gas circulation flow in transient condition. Then there were different final gas temperature distributions on the basis of the result of steady-state analysis. This phenomenon has a potential for it's own metastable condition. Therefore it was necessary to design gas cooling flow pattern without ...
Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; Sudo, Toshiyuki; Hayashi, Shinichiro;
JNC TN8410 2000-006, 116 Pages, 2000/04
JNC-TN8410-2000-006.pdf:2.77MB
Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.
*; *; *; *
JNC TJ3410 2000-020, 80 Pages, 2000/03
JNC-TJ3410-2000-020.pdf:41.34MB
no abstracts in English
Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Arita, Tadaaki*; Maruyama, T.*; Kakuta, Toshiya*; Konishi, Satoshi; Enoeda, Mikio; Ohira, Shigeru; Hayashi, Takumi; et al.
Nuclear Fusion, 40(3Y), p.515 - 518, 2000/03
Times Cited Count：6 Percentile：21.01(Physics, Fluids & Plasmas)no abstracts in English
Kawachi, Akinori; ; Miyajima, Kazutoshi
JAERI-Tech 99-028, 51 Pages, 1999/03
no abstracts in English
Yamanishi, Toshihiko; Konishi, Satoshi; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Maruyama, T.*; Kakuta, Toshiya*; Ohira, Shigeru; Nakamura, Hirofumi; Kobayashi, Kazuhiro; et al.
Fusion Technology, 34(3), p.536 - 540, 1998/11
no abstracts in English
PNC TN1410 98-018, 69 Pages, 1998/09
This report collects the results of safety research in nuclear fuel cycle at power reactor ans nuclear fuel development corporation, in order to answer to the questionnaire of OECD/NEA. The questionnaire request to inelude information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: (1) Recently completed reseach projects (2) Ongoing (current) research projects achievements on following items are omitted by request of oecd/nea. Uranium mining and milling, uranium refining and conversion to UF
, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning we select topics from the fields of a (1) Nuclear installation, (2) Seismic, and (3) PSA, in projects from frame of annual safety research plan for nuclear installations established by nuclear safety ...
Haga, Yoshinori; Homma, Tetsuo*; Yamamoto, Etsuji; Okuni, H.*; Onuki, Yoshichika*; Ito, Mitsuo; Kimura, Noriaki*
Japanese Journal of Applied Physics, 37(6A), p.3604 - 3609, 1998/06
Times Cited Count：39 Percentile：81.79(Physics, Applied)no abstracts in English
Haga, Yoshinori; Yamamoto, Etsuji; Kimura, Noriaki*; *; Okuni, H.*; Onuki, Yoshichika*
J. Magn. Magn. Mater., 177-181, p.437 - 438, 1998/00
Times Cited Count：8 Percentile：44.25(Materials Science, Multidisciplinary)no abstracts in English
Haga, Yoshinori; Yamamoto, Etsuji; Homma, Tetsuo*; Kimura, Noriaki*; *; Okuni, H.*; Aoki, Dai*; Ito, Mitsuo; Onuki, Yoshichika*
Physics of Strongly Correlated Electron Systems (JJAP Series 11), p.269 - 271, 1998/00
no abstracts in English
