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Aoyama, Takafumi; Maeda, Shigetaka; Maeda, Yukimoto; Suzuki, Soju
Journal of Nuclear and Radiochemical Sciences, 6(3), p.279 - 282, 2005/12
The present study examines the potential for the demonstration of fission product transmutation in the experimental fast reactor JOYO at JNC's Oarai Engineering Center. The possibility of creating a highly-efficient transmutation irradiation field by loading neutron moderating subassemblies in the reflector region of JOYO was examined in a series of scoping calculations. A cluster of reflector subassemblies was replaced with beryllium or zirconium hydride (ZrH1.65) moderated subassemblies. These moderated subassemblies surrounded one central test subassembly that would contain 
Tc or 
I target material. The Tc transmutation rate was 16.2% using ZrH
and 13.9% using beryllium as moderator. As a result of this study, basic characteristics of LLFP transmutation in JOYO using relevant moderator materials were investigated and the future feasibility was shown.
W/Re generatorsMatsuoka, Hiromitsu; Hashimoto, Kazuyuki; Hishinuma, Yukio*; Ishikawa, Koji*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*; Uchida, Shoji*
Journal of Nuclear and Radiochemical Sciences, 6(3), p.189 - 191, 2005/12
Applicability of Mo adsorbent PZC(Poly Zirconium Compound) for W/Re generator was investigated. Long term stability of adsorption of W to the PZC column, elution of Re from PZC column, desorption of 
from PZC column, and labeling of Hydroxyethylidene Diphosphonic Acid(HEDP) and Mercaptoacetyltriglycine(MAG3) with Re eluted from PZC column were tested. The PZC generator gave reproducible Re elution yields with low W parent breakthrough for a long period of time(about 5 months), that is the W/Re generator using PZC has a potential for practical use.
ReHashimoto, Kazuyuki; Wan, K. W. H. B. B.*; Matsuoka, Hiromitsu
Journal of Nuclear and Radiochemical Sciences, 6(3), p.193 - 196, 2005/12
The radioisotopes of rhenium (
Re and Re) are attractive radionuclides for radiotherapy because of their energetic beta particles and gamma rays suitable for imaging. Mercaptoacetyltriglycine, MAG3 (N
S ligand), is a useful bifunctional ligand in labeling monoclonal antibodies with metallic radionuclides. In this study, the labeling of MAG3 with carrier-free Re from a W/Re generator was investigated in detail. The Re-MAG3 complex was synthesized by the direct labeling method and by the indirect labeling method using a transfer ligand (citric acid or gluconic acid). The dependence of the labeling yield upon the reaction conditions such as the concentrations of tin(II) chloride dihydrate as a reducing agent, S-benzoyl MAG3 and the transfer ligand, pH, temperature, reaction time and the addition of a carrier was examined. The labeling yield of Re-MAG3 synthesized by the all method was over 90% under the optimum conditions.
Asakura, Toshihide; Kim, S.-Y.; Morita, Yasuji; Ozawa, Masaki*
Journal of Nuclear and Radiochemical Sciences, 6(3), p.267 - 269, 2005/12
An electrolytic extraction (EE) method, i.e. electro-reductive deposition, of Tc from nitric acid aqueous solution was studied for future reprocessing. After 30 min of constant potential electrolysis by carbon electrode at -0.3 V vs. SSE (Standard Silver Electrode), Tc concentration in 3 M nitric acid decreased to 93 % of the initial value, which corresponds to 7 % of deposition. With co-existence of Pd, the value reached to 15 % of deposition equivalent by electrolysis at 
0.0 V vs. SSE for 60 min. An acceleration effect of Pd on Tc deposition (promoter effect) was suggested. The concentration, however, increased to the initial value after further electrolysis and competing re-dissolution of deposited Tc was also suggested. In cyclic voltammetry measurements, it was found that the deposit from Tc-Pd-Ru-Rh solution dissolved easier than that from Pd-Ru-Rh did. In electrolyzed Tc solution, an absorption peak at 482 nm was found. It can be attributed to the complex with nitrite anion, and the complex formation is proposed as one possible mechanism of Tc re-dissolution.
Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji
Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12
Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO
fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.
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.
Nagame, Yuichiro
Journal of Nuclear and Radiochemical Sciences, 6(3), p.205 - 210, 2005/12
no abstracts in English
Takeishi, Minoru; Hiyama, Yoshinori*; Mizutani, Tomoko; Watanabe, Hitoshi; Maruo, Yoshihiro
Proceedings of International Symposium on Technetium -Science and Utilization- (IST 2005), p.47 - 48, 2005/00
To investigate of Tc-99 release, large amount of liquid samples (8-litter) were used for the analysis, which was developed by JNC. The Tc-99 release in the liquid effluent from TRP during 1999-2000 were measured and the normalized release of Tc-99, which were normalized by annual energy generated (GWa) derived from the treated spent fuels, were compared with that of other radionuclides.
TcFurutaka, Kazuyoshi; Harada, Hideo; Nakamura, Shoji; Kato, Toshio; Fujii, Toshiyuki*; Yamana, Hajimu*; Raman, S.*
IST 2005 Abstracts, 2511, p.51, P. 51, 2004/00
In order to experimentally determine cross section of thermal-neutron capture reaction byTc, the following studies have been performed: (1) Measurement of the cross section using an activation method in which rays inRu were observed, (2) Measurement of emission probabilities of rays inRu, and (3) Measurement of the Cross section from yields of the prompt rays emitted in the reaction. In this presentation, details of these studies will be reviewed, and the obtained results will be compared to others. Possible improvements of the experimental methods will also be presented.
