Preliminary investigation of pretreatment methods for liquid scintillation measurements of environmental water samples using ion exchange resins

Nakasone, Shunya*; Yokoyama, Sumi*; Takahashi, Tomoyuki*; Ota, Masakazu; Kakiuchi, Hideki*; Sugihara, Shinji*; Hirao, Shigekazu*; Momoshima, Noriyuki*; Tamari, Toshiya*; Shima, Nagayoshi*; et al.

Plasma and Fusion Research (Internet), 15, p.2405027_1 - 2405027_3, 2020/05

https://doi.org/10.1585/pfr.15.2405027

A quick preprocessing system for tritium analysis of environmental samples is important to judge environmental influence of tritium releases due to accident or tritium-handling facilities. Analysis of tritium in water samples with liquid scintillation counting method requires removal of impurities such as organic matter and ion species from water samples. Generally, a distillation method is adopted as a pretreatment of analysis for tritium; however, the distillation method is a time-consuming process. The aim of this study is to evaluate a rapid pretreatment method for tritium analysis with ion exchange resin. From batch and column experiments that used inland water and ion exchange resin, we confirmed removals of impurities of the water sample and that the removal of impurities was possible for a short time (by 5 minutes).

Behavior of NbSn cable assembled with conduit for ITER central solenoid

Nabara, Yoshihiro; Suwa, Tomone; Takahashi, Yoshikazu; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200305_1 - 4200305_5, 2015/06

https://doi.org/10.1109/TASC.2014.2360562

Investigation of degradation mechanism of ITER CS conductor sample using TAKUMI

Hemmi, Tsutomu; Harjo, S.; Kajitani, Hideki; Nabara, Yoshihiro; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Koizumi, Norikiyo; Abe, Jun; Gong, W.; Aizawa, Kazuya; et al.

KEK Progress Report 2013-4, p.45 - 47, 2013/11

https://lib-extopc.kek.jp/preprints/PDF/2013/1323/1323004.pdf

The gradual degradation was observed in the results for ITER CS conductor samples. To investigate its origin, the internal strain in the sample after the testing was successfully measured using a neutron diffraction technique non-destructively. Up to now, the transverse electromagnetic loading has been considered as an origin of the degradation due to the local bending at the high loading side (HLS). However, as a result of the neutron diffraction measurement, the large bending at the LLS of the HFZ was found. The large bending was considered as an origin of the strand buckling due to the large void generated by the transverse electromagnetic loading and the thermally induced residual compressive strain. For the improvement of the conductor performance on the strand buckling, the shorter twisting pitch (STP) can be considered. The result of the SULTAN testing of the conductor sample with STP found very effective, and the performance degradation was negligible.

Development of multi-purpose MW gyrotrons for fusion devices

Minami, Ryutaro*; Kariya, Tsuyoshi*; Imai, Tsuyoshi*; Numakura, Tomoharu*; Endo, Yoichi*; Nakabayashi, Hidetaka*; Eguchi, Taku*; Shimozuma, Takashi*; Kubo, Shin*; Yoshimura, Yasuo*; et al.

Nuclear Fusion, 53(6), p.063003_1 - 063003_7, 2013/06

https://doi.org/10.1088/0029-5515/53/6/063003

Test results and investigation of Tcs degradation in Japanese ITER CS conductor samples

Hemmi, Tsutomu; Nunoya, Yoshihiko; Nabara, Yoshihiro; Yoshikawa, Masatoshi*; Matsui, Kunihiro; Kajitani, Hideki; Hamada, Kazuya; Isono, Takaaki; Takahashi, Yoshikazu; Koizumi, Norikiyo; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4803305_1 - 4803305_5, 2012/06

https://doi.org/10.1109/TASC.2011.2178370

To characterize the performance of the CS conductor, a CS conductor sample was tested in the SULTAN facility at CRPP. As a result of the cyclic test up to 1000 cycles, measured Tcs was in good agreement with the expected Tcs, which is calculated by the characteristics of the NbSn strands and the designed strain. However, continuous degradation of Tcs was observed after 1000 cycles. The degradation of Tcs was around 0.6 K from 1000 cycles to 6000 cycles. On the other hand, the degradation of Tcs by cyclic operation is nearly 0.1 K from 1000 cycles to 10,000 cycles in the CS Insert test at JAEA in 2000. To investigate the causes for the degradation of Tcs, the following items are performed; (1) strain measurement by neutron diffraction, (2) strain measurement by sample cuttings, (3) strand position observation, (4) visual inspection on strands, (5) filament breakage observation, (6) modeling and calculation of the degradation. Detailed results will be presented and discussed.

The H-Invitational Database (H-InvDB); A Comprehensive annotation resource for human genes and transcripts

Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.

Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01

https://doi.org/10.1093/nar/gkm999

Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.

Report of lower end plug welding, and test and inspection for the JOYO 6th refueling core fuel assembly

Kajiyama, Tadashi; Numata, Kazuaki; Otani, Seiji; ; ; Goto, Tatsuro*; Takahashi, Hideki*

JNC TN8440 2000-010, 45 Pages, 2000/02

JNC-TN8440-2000-010.pdf:1.45MB

This report describes about procedure and consequence of the welding process of the cladding tube and the lower end plug, the process of the test and inspection and the process of shipment for the 6th refueling core fuel assembly (46 fuel assemblies) of the experimental fast reactor JOYO. These works were carried out on July, 1996 from January, 1993 in Tamatukuri inspection branch of quality assurance section, technical administration division, plutonium fuel center. The 6th refueling core fuel assemblies are two kinds of the fuel assembly (1) and (2). The material of the lower end plug and the cladding tube used for the fuel assembly (1) is the type 316 stainless steel grade (here in after referred to as SUS316 grade) and austenitic stainless steel of high nickel content (here in after referred to as PNC 1520). That material used for the fuel assembly (2) is all SUS316 grade. The result of welding and the inspection is shown in the following table.

An investigation report on the defective occurrence of the lower end plug welded section for JOYO MK-III.; An investigation result about the inclusion occurrence

Kajiyama, Tadashi; Numata, Kazuaki; Otani, Seiji; Goto, Tatsuro*; Takahashi, Hideki*

JNC TN8430 2000-007, 44 Pages, 2000/02

JNC-TN8430-2000-007.pdf:5.32MB

Fabrication of the cladding tube with the lower end plug for the core fuel assembly of the experimental fast reactor JOYO and the proto-type fast breeder reactor MONJU has been performed by Tamatsukuri inspection branch of quality assurance section, Technical administration division, Plutonium fuel center since 1989. The fabrication process of the cladding tube with the lower end plug consists of numbering process of fuel element number to the lower end plug, welding process of the lower end plug and the cladding tube, and inspection process after welding (visual inspection, dimensional inspection and X-ray radiography). The processing of cladding tube with the lower end plug which is used for the initial loading core fuel assembly of JOYO MK-III has been carried out from August to May in 1996. The many tungsten inclusions were observed by X-ray radiography in the welds of the cladding tube with the lower end plug that were fabricated in the fourth fabrication campaign performed from July to August in 1996. The investigation of the causes was carried out about the welding process of the cladding tube and the lower end plug based on the fabrication record. The following three items were confirmed as a result. (1)As for the ingredients of inclusions observed by the X-ray radiography, it was proved by EPMA(Electron Probe X-ray Micro-analyzer) analysis that it was the same as the tungsten electrode. (2)Cracks, chips and consumption were observed in the tip of the electrodes used for welding of the lower end plug. And, cracks and chips were observed in the electrodes as well which hadn't been used. (3)It was proved that the tip of the electrode was exhausted remarkably when the distance between the tip of the electrode and the welding section became less than 0.08mm. (here in after to as the distance between the electrodes) Based on the above result, examination of reappearance for the inclusion generation was performed simulating the shape of cracks and chips ...

Design study on large-scale mercury loop for engineering test of target of high-intensity proton accelerator

Hino, Ryutaro; Haga, Katsuhiro; ; ; ; Kaminaga, Masanori; Sudo, Yukio;

JAERI-Tech 97-009, 50 Pages, 1997/03

JAERI-Tech-97-009.pdf:3.43MB

no abstracts in English

Development of a 240mm bore-13T superconducting coil for large scale conductor testing

Nishi, Masataka; Ando, Toshinari; Isono, Takaaki; Sugimoto, Makoto; Koizumi, Norikiyo; Yoshida, Kiyoshi; Kawano, Katsumi; Takahashi, Yoshikazu; ; Tsuji, Hiroshi; et al.

IEEE Transactions on Magnetics, 28(1), p.597 - 600, 1992/01

https://doi.org/10.1109/20.119947

no abstracts in English