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Journal Articles

Prototype manufacturing of small tritium target inside JAEA

Tanaka, Shigeru; Abe, Yuichi; Kawabe, Masaru; Kutsukake, Chuzo; Oginuma, Yoshikazu; Yamada, Masayuki; Suzuki, Takumi; Yamanishi, Toshihiko; Konno, Chikara

Journal of Plasma and Fusion Research SERIES, Vol.9, p.338 - 341, 2010/08

We have conducted a small tritium target production R&D for FNS inside JAEA. The tritium target is produced by adsorbing tritium in a thin titanium layer. Since titanium is very active to oxygen, glow discharge cleaning was carried out to remove an oxidation film of the titanium surface. Through many tests with deuterium, we found out that it was not an oxidation film but humidity to disturb tritium absorption. The following procedures were necessary; (1) to outgas the inside of an absorption chamber, (2) to keep environmental humidity under 3% in handling the titanium-deposited substrate, (3) to keep the titanium-deposited target substrate in the vacuum. The DT neutron generation performance of the tritium target produced with the above procedures was the same as that with discharge cleaning. The manufacture condition of the small target was established.

Journal Articles

Measurement of reaction rate distribution in partial mockups for the ITER TBM with DT neutrons

Sato, Satoshi; Takakura, Kosuke; Ochiai, Kentaro; Kondo, Keitaro; Tatebe, Yosuke; Onishi, Seiki; Wada, Masayuki*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; et al.

Fusion Science and Technology, 56(1), p.227 - 231, 2009/07

 Times Cited Count:1 Percentile:88.61(Nuclear Science & Technology)

Previously DT neutronics experiments were performed by using partial blanket mockups for Japanese ITER test blanket module at JAEA FNS, and tritium production rates (TPR) inside blanket mockups were measured in details. The calculation with the nuclear data library FENDL-2.1 and Monte Carlo code MCNP4C agreed well with most of the measured TPRs within uncertainty of 10%. On the other hand, overestimations were found for the TPR in the experiment with a reflector and the TPR around the boundary between the rear part of the breeder layer and the beryllium layer by more than 10%. In order to confirm this concern, we measured reaction rate distribution in the partial blanket mockups with DT neutrons with two solid breeder blanket partial mockups, (Be/Li$$_{2}$$TiO$$_{3}$$/Be, SS316/Li$$_{2}$$TiO$$_{3}$$/SS316). Experiments were performed with and without a neutron source reflector. In order to measure reaction rate distributions, the activation foil method was applied using Nb and Au foils in this study. Experimental analyses were performed by MCNP4C with FENDL-2.1. Calculation results to experimental ones (C/Es) on the Au reaction rate with a reflector were larger than those without one. Detailed results are presented in this conference.

Journal Articles

Neutronics experimental study on tritium production in solid breeder blanket mockup with neutron reflector

Sato, Satoshi; Verzilov, Y.*; Ochiai, Kentaro; Wada, Masayuki*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Seki, Masakazu; Oginuma, Yoshikazu*; Kawabe, Masaru*; et al.

Journal of Nuclear Science and Technology, 44(4), p.657 - 663, 2007/04

 Times Cited Count:5 Percentile:59.58(Nuclear Science & Technology)

Neutronics experiments have been performed for the solid breeder blanket using a DT neutron source at the FNS facility in JAEA. We have applied the blanket mockup composed of two enriched Li$$_{2}$$TiO$$_{3}$$ and three beryllium layers, and measured the detailed spatial distribution of the tritium production rate (TPR) using enriched Li$$_{2}$$CO$$_{3}$$ pellets. TPRs in the pellets have been measured by a liquid scintillation counter. Experiments have been done under a condition with a neutron reflector surrounding the DT neutron source. Numerical simulations have been performed using the MCNP-4C with the FENDL-2.0 and JENDL-3.3. The ranges of ratios of calculation results to experimental ones (C/Es) are 0.97-1.17 concerning with local TPR, and 1.04-1.09 for the integrated tritium production. It is found that the total integrated tritium production, which corresponds to tritium breeding ratio, can be predicted within uncertainty of 10% using the Monte Carlo calculation code and latest nuclear data libraries.

Journal Articles

Application of react-and-wind method to D-shaped test coil using the 20 kA Nb$$_{3}$$Al conductor developed for JT-60SC

Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; Koizumi, Norikiyo; Matsui, Kunihiro; Ando, Toshinari*; Hamada, Kazuya; Hara, Eiji*; Imahashi, Koichi*; Ishida, Shinichi; et al.

IEEE Transactions on Applied Superconductivity, 14(2), p.1535 - 1538, 2004/06

 Times Cited Count:1 Percentile:87.89(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development of the Nb$$_{3}$$Al D-shaped coil fabricated by react-and-wind method for JT-60 superconducting Tokamak

Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; Koizumi, Norikiyo; Matsui, Kunihiro; Ando, Toshinari*; Hamada, Kazuya; Hara, Eiji*; Imahashi, Koichi*; Ishida, Shinichi; et al.

Proceedings of 6th European Conference on Applied Superconductivity (EUCAS 2003), p.400 - 407, 2003/00

Toroidal field coils (TFC) of the JT-60SC consist of 18 D-shape coils. The maximum magnetic field is 7.4 T at an operational current of 19.4 kA. An advanced Nb$$_{3}$$Al superconductor was developed for the TFC conductor material in JAERI. The Nb$$_{3}$$Al has lower strain sensitivity on superconducting performances, and allows us to fabricate the TFC by react-and-wind (R&W) method that makes that the coil fabrication with high reliability becomes easier and the fabrication cost becomes lower. To demonstrate the coil fabrication by R&W method, a two-turn D-shape coil was developed. The D-shape coil was tested at 4.3-4.4K and 7-12T. Measured critical current (Ic) was 30 kA at 7.3 T and 4.4 K. Using the measured conductor and strand Ic values, the strain of the conductor was estimated to be -0.6%. The Ic-B-T characteristic expected by an empirical equation substituting this strain shows that the required temperature margin for TFC is satisfied. Thus, the R&W method was demonstrated to be the applicable fabrication method of the TFC.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:22.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:53 Percentile:15.76(Physics, Fluids & Plasmas)

no abstracts in English

Oral presentation

ITER/TBM neutronics experiments at FNS, 1; Experiment

Ochiai, Kentaro; Sato, Satoshi; Takakura, Kosuke; Yamauchi, Michinori*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Seki, Masakazu; Kawabe, Masaru*; Konno, Chikara; et al.

no journal, , 

The test blanket module (TBM), water cooled pebble bed type, which is to be installed in ITER has been designed in JAEA. The TBM is made up of water cooling system with a kind of low activation ferrite, beryllium as neutron breeder, $$^{6}$$Li enriched Li$$_{2}$$TiO$$_{3}$$ or Li$$_{2}$$O pebble as tritium breeding material. To evaluate the nuclear properties, we have carried out some DT neutronics experiments with TBM mock up assemblies in the Fusion Neutronics Source (FNS) and one of the TBM nuclear properties, the tritium production rate (TPR), in the Li$$_{2}$$TiO$$_{3}$$ layer has been clarified by means of a liquid scintillation counter method with Li$$_{2}$$CO$$_{3}$$ pellets or Li$$_{2}$$O pebbles.

Oral presentation

Progress on blanket neutronics study

Sato, Satoshi; Takakura, Kosuke; Ochiai, Kentaro; Wada, Masayuki*; Onishi, Seiki; Iida, Hiromasa; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Kawabe, Masaru; et al.

no journal, , 

no abstracts in English

Oral presentation

Manufacturing of small tritium target for DT neutron generator

Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Kawabe, Masaru*; Suzuki, Takumi; Yamada, Masayuki; Yamanishi, Toshihiko; Konno, Chikara

no journal, , 

A small tritium target for Fusion Neutronics Source(FNS) was successfully produced at the Tritium Processing Laboratory(TPL) in JAEA for the first time and examined the performance of the target. The small tritium target is produced with absorbing tritium in evaporated titanium layer on copper alloy substrate. Titanium metal is very active to oxygen. The surface of titanium quickly oxidizes on exposure to air and the oxidized titanium does not absorb enough tritium. Trough many tests we found out that a glow discharge cleaning system with argon gas could remove the oxidizes titanium surface adequately. Tritium amount of about 400 GBq was successfully absorbed to the cleaned titanium layer at TPL. The produced tritium target performance was tested at FNS. The tritium distribution in titanium was almost flat, the initial DT neutron generation rate was 1.7E11 n/s/mA and the attenuation of DT neutron generation rate with beam irradiation quantity was small.

Oral presentation

The Production of a tritium target for FNS

Tanaka, Shigeru; Kutsukake, Chuzo; Abe, Yuichi; Kawabe, Masaru*; Suzuki, Takumi; Yamada, Masayuki; Yamanishi, Toshihiko; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

Manufacture and characterization of titanium tritium target

Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Kawabe, Masaru*; Suzuki, Takumi; Yamada, Masayuki; Yamanishi, Toshihiko; Konno, Chikara

no journal, , 

Last year FNS successfully produced a small tritium target at the Tritium Processing Laboratory (TPL) in JAEA for the first time and examined the performance of the target. The small tritium target is produced with absorbing tritium in evaporated thin titanium layer on cap-shaped copper-alloy substrate. Titanium metal is very active to oxygen. The surface of titanium quickly oxidizes on exposure to air and the oxidized titanium does not absorb enough tritium. Through many tests we carried out that a glow discharge cleaning system with argon gas could remove the oxidized titanium surface adequately. Tritium of about 400 GBq was successfully absorbed to the surface of cleaned titanium layer on copper-alloy substrate at TPL which can handle a large amount of tritium in JAEA. The produced tritium target was tested at FNS. This performance was very good performance for fusion neutronics research.

Oral presentation

Manufacturing of large tritium target for DT neutron generation inside JAEA

Abe, Yuichi; Tanaka, Shigeru; Kawabe, Masaru*; Oginuma, Yoshikazu; Kutsukake, Chuzo; Yamada, Masayuki; Suzuki, Takumi; Yamanishi, Toshihiko; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

Prototype manufacturing of large tritium target for DT neutron source inside JAEA

Abe, Yuichi; Tanaka, Shigeru; Oginuma, Yoshikazu; Kawabe, Masaru*; Yamada, Masayuki; Suzuki, Takumi; Yamanishi, Toshihiko; Konno, Chikara

no journal, , 

We succeeded in producing a large tritium target for Fusion Neutronics Source (FNS) inside JAEA. The large tritium target is produced by absorbing tritium in an evaporated thin titanium layer on disk-shaped copper-alloy substrate. It is essential to remove out-gases, particularly humidity, from the titanium layer and substrate because out-gases block the tritium absorption. We developed an adsorption chamber and we found out a condition for the tritium adsorption through many deuterium adsorption tests to the titanium instead of tritium. The tritium adsorption chamber is installed in the glove box of Tritium Processing Laboratory (TPL), and we manufactured a large tritium target. The amount of the adsorbed tritium of the large target was about 26 TBq, and the initial DT neutron generation rate was 1.7$$times$$10$$^{11}$$n/sec/mA. This performance was very good compared with commercial based large tritium targets.

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