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Journal Articles

Development and testing of large-scale nuclear components and remote handling system in JAERI

Seki, Masahiro; Ohara, Yoshihiro; Tada, Eisuke; Akiba, Masato

Fusion Engineering and Design, 51-52, p.941 - 948, 2000/11

 Times Cited Count:0 Percentile:100

no abstracts in English

JAEA Reports

Trial manufacturing of copper-carbon steel composite overpack

*; *; Tanai, Kenji

JNC-TN8400 99-049, 94 Pages, 1999/11

JNC-TN8400-99-049.pdf:6.63MB

This paper reports the results of design analysis and trial manufacturing of copper-carbon steel composite overpacks. The overpack is one of the key components of the engineered barrier system, hence, it is necessary to confirm the applicability of current technique in their manufacture. The Copper-Carbon steel composite overpack consists of a double container, an outer vessel made of oxygen-free, high-purity copper as the corrosion allowance material, and an inner vessel made of carbon steel as the pressure-resistant material. The trial manufacturing in this time, only the copper outer vessel has been fabricated. Both oxygen-free copper and oxygen-free phosphorus copper were used as materials for the outer vessel. For the shell and bottom portion, these materials were formed integrally by a backward extrusion method. For sealing the top cover plate to the main body, an electron-beam welding method was applied. After manufacturing, mechanical testing of specimens from the copper vessels were carried out. It was confirmed that current technique has sufficient feasibility to manufacture outer vessel. In addition, potential for irradiation embrittlement of the inner carbon-steel vessel by irradiation from vitrified waste over the life time of the overpack has been analyzed. It was shown that the small degree of irradiation embrittlement gives no significant impact on the pressure resistance of the carbon-steel vessel. Future research and development items regarding copper-carbon steel composite overpacks are also discussed.

JAEA Reports

Trial manufacturing of titanium-carbon steel composite overpack

*; *; Tanai, Kenji

JNC-TN8400 99-048, 85 Pages, 1999/11

JNC-TN8400-99-048.pdf:4.31MB

This paper reports the results of design analysis and trial manufacturing of full-scale titanium-carbon steel composite overpacks. The overpack is one of the key components of the engineered barrier system, hence, it is necessary to confirm the applicability of current technique in their manufacture. The required thickness was calculated according to mechanical resistance analysis, based on models used in current nuclear facilities. The Adequacy of the calculated dimensions was confirmed by finite-element methods. To investigate the necessity of a radiation shielding function of the overpack, the irradiation from vitrified waste has been calculated. As a result, it was shown that shielding on handling and transport equipment is a more reasonable and practical approach than to increase thickness of overpack to attain a self-shielding capability. After the above investigation, trial manufacturing of full-scale model of titanium-carbon steel composite overpack has been carried out. For corrosion-resistant material, ASTM Grade-2 titanium was selected. The titanium layer was bonded individually to a cylindrical shell and flat cover plates (top and bottom) made of carbon steel. For the cylindrical shell portion, a cylindrically formed titanium layer was fitted to the inner carbon steel vessel by shrinkage. For the flat cover plates (top and bottom), titanium plate material was coated by explosive bonding. Electron beam welding and gas metal arc welding were combined to weld of the cover plates to the body. No significant failure was evident from inspections of the fabrication process, and the applicability of current technology for manufacturing titanium-carbon steel composite overpack was confirmed. Future research and development items regarding titanium-carbon steel composite overpacks are also discussed.

JAEA Reports

Design concepts for overpack

*; *; Tanai, Kenji

JNC-TN8400 99-047, 54 Pages, 1999/11

JNC-TN8400-99-047.pdf:3.16MB

This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.

JAEA Reports

None

; ; ; ; ;

JNC-TN8410 98-007, 201 Pages, 1998/11

JNC-TN8410-98-007.pdf:30.03MB

None

Journal Articles

R&D activities for superconducting proton linac at JAERI

Ouchi, Nobuo; Kusano, Joichi; Akaoka, Nobuo*; B.Fechner*; Hasegawa, Kazuo; Takeuchi, Suehiro; Mizumoto, Motoharu; Saito, Kenji*; Noguchi, Shuichi*; *; et al.

Proc. of 1st Asian Particle Accelerator Conf. (APAC98), p.77 - 79, 1998/11

no abstracts in English

JAEA Reports

None

; ; *; ; Takeda, Seiichiro

PNC-TN8410 98-060, 74 Pages, 1998/03

PNC-TN8410-98-060.pdf:4.43MB

None

Journal Articles

Development of superconducting cavities for high intensity proton accelerator at JAERI

Ouchi, Nobuo; Kusano, Joichi; Akaoka, Nobuo*; Takeuchi, Suehiro; Hasegawa, Kazuo; Mizumoto, Motoharu; Inoue, Hitoshi*; *; Noguchi, Shuichi*; *; et al.

Development of Large Scale Superconducting Radio Frequency (SRF) Technologies, p.50 - 55, 1998/00

no abstracts in English

JAEA Reports

None

PNC-TJ1600 97-002, 97 Pages, 1997/03

PNC-TJ1600-97-002.pdf:4.13MB

no abstracts in English

Journal Articles

The HTTR reactor pressure vessel and its integrity against a PTS event

Kurihara, Ryoichi

Nucl. Eng. Des., 172(3), p.317 - 325, 1997/00

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Fabrication and test of a superconducting single cell cavity for the high intensity proton linac

Ouchi, Nobuo; Kusano, Joichi; Noguchi, Shuichi*; Saito, Kenji*; Inoue, Hitoshi*; *; *; Mizumoto, Motoharu; B.Fechner*; Mukugi, Ken*; et al.

Proc. of 22nd Linear Accelerator Meeting in Japan, p.167 - 169, 1997/00

no abstracts in English

Journal Articles

Design and development work for a superconducting proton linac at JAERI

Ouchi, Nobuo; Kusano, Joichi; Akaoka, Nobuo*; Takeuchi, Suehiro; B.Fechner*; Hasegawa, Kazuo; Mizumoto, Motoharu; Inoue, Hitoshi*; *; Noguchi, Shuichi*; et al.

Proc. of 8th Workshop on RF Superconductivity, 1, p.22 - 26, 1997/00

no abstracts in English

Journal Articles

Proton linac activities in JAERI

Ouchi, Nobuo; Kusano, Joichi; Akaoka, Nobuo*; Takeuchi, Suehiro; B.Fechner*; Hasegawa, Kazuo; Mizumoto, Motoharu; Inoue, Hitoshi*; *; Noguchi, Shuichi*; et al.

Proc. of 8th Workshop on RF Superconductivity, 1, p.12 - 21, 1997/00

no abstracts in English

JAEA Reports

None

PNC-TN8420 94-003, 21 Pages, 1994/03

PNC-TN8420-94-003.pdf:0.52MB

None

JAEA Reports

Development of the ultrasonic testing equipment for FBR; Results of R&D

; ; ; ;

PNC-TN9420 92-014, 125 Pages, 1992/11

PNC-TN9420-92-014.pdf:6.57MB

This report decribes the development of multi-array type probe for FBR steamgenerator tube. We studied integration between three kinds of probes, which were for axial flaw, for circumferential flaw and for wall thickness flaw, detecting method of accuracy locating probe and basic composition of multi-channel detector. It was comfirmed that each devices had object performance in performance test. We shall use this results to study design and manufacture of ultrasonic testing equipment for steamgenerator of FBR Monju.

Journal Articles

Research and development on selecting first wall material of JT-60

Nakamura, H.; ; Yamamoto, M.;

Journal of Nuclear Science and Technology, 25(1), p.81 - 91, 1988/01

no abstracts in English

Journal Articles

Journal Articles

JAEA Reports

Fabrication of HgI$$_{2}$$ Nuclear Radiation Detectors

*; ;

JAERI-M 8478, 133 Pages, 1979/10

JAERI-M-8478.pdf:9.04MB

no abstracts in English

JAEA Reports

Design and Tests of the Modified Control Rod Drive System; Modification of JRR-2

; ; ; ;

JAERI-M 8137, 113 Pages, 1979/03

JAERI-M-8137.pdf:4.48MB

no abstracts in English

23 (Records 1-20 displayed on this page)