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Journal Articles

Main features of ITER vacuum vessel and approach to code application

Nakahira, Masataka; Takeda, Nobukazu; Hada, Kazuhiko; Tada, Eisuke; Miya, Kenzo*; Asada, Yasuhide*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/04

The special features of Vacuum Vessel (VV) of International Thermonuclear Experimental Reactor (ITER) are complicated structure and electromagnetic load. The VV is torus shaped, double-walled structure with ribs. The electromagnetic force is not uniform. Thus the rules for axisymmetric structures and loading are not effective for ITER VV. The double ミwalled structure requires one-sided welding joints with no possibility of access from the other side. Every joints between outer wall and rib and field joints are this type. The joint between outer wall and rib is special T-joint with partial penetration. To cover these special issues on ITER VV, a new code is under development. Supporting R&Ds are planned to be material tests to obtain joint efficiency and fatigue reduction factor, UT sensitivity tests, sensitivity tests on crevice corrosion and examination-free welding for application to field joints. This paper describes the special features of ITER VV from code stand point, concept of new code and R&Ds to apply the new code to ITER VV.

Journal Articles

Numerical prediction of secondary flows in complex areas using concept of local turbulent Reynolds number

Kriventsev, V.; Ninokata, Hisashi; Yamaguchi, Akira; Ohshima, Hiroyuki

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/04

A new model of turbulence is proposed for the estimation of Reynolds stresses in turbulent fully-developed flow in a wall-bounded straight channel of an arbitrary shape. The main idea of a Multi-Scale Viscosity(MSV) model can be expressed in the following phenomenological rule:A local deformation of axial velocity can generate the turbulence with the intensity that keeps the value of the localturbulent Reynolds number below some critical one. Therefore,in MSV,the only empirical parameter is the critical Reynolds number. Since MSV can naturally predict turbulent viscosity anisotropy in directions normal and parallel to the wall,it is capable to calculate secondary flows in thecross-section of the rod bundle.

Journal Articles

Systematic source term analyses for level 3 PSA of a BWR with Mark-II type containment with THALES-2 code

Ishikawa, Jun; Muramatsu, Ken; Sakamoto, Toru*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

no abstracts in English

Journal Articles

New cryogenic steels and design approach for ITER superconducting magnet system

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Hada, Kazuhiko; Tada, Eisuke

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

The Japan Atomic Energy Research Institute (JAERI) has conducted to develop a new design code for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER), which will be formed as a code case of ASME B&PV Code Section III, division 4, in collaboration with the ASME international. The new design code will also include the several new techniques and materials developed for each components of ITER. This paper describes the new cryogenic steels used in the magnet system and the design approach with taking account of unique features of the ITER superconducting magnets.

Journal Articles

Roll wave effects on annular condensing heat transfer in horizontal PCCS condenser tube

Kondo, Masaya; Nakamura, Hideo; Anoda, Yoshinari; Saishu, Sadanori*; Obata, Hiroyuki*; Shimada, Rumi*; Kawamura, Shinichi*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 9 Pages, 2002/00

no abstracts in English

Journal Articles

Numerical visualization of water-vapor flow configurations in fusion reactors during ingress of coolant events

Ose, Yasuo*; Takase, Kazuyuki; Yoshida, Hiroyuki; Akimoto, Hajime

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

no abstracts in English

Journal Articles

Multi-dimensional thermal-hydraulic analysis for horizontal type PCCS

Arai, Kenji*; Kurita, Tomohisa*; Nakamaru, Mikihide*; Fujiki, Yasunobu*; Nakamura, Hideo; Kondo, Masaya; Obata, Hiroyuki*; Shimada, Rumi*; Yamaguchi, Ken*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

Journal Articles

STUDIES ON APPLICABILITY OF SMOKE SENSORS AS A SODIUM LEAK MONITORING SYSTEM

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

DEVELOPMENT OF MICROPHONE LEAK DETECTION SYSTEM AT FUGEN NPP

Shimans; Iijima, Takashi;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

SENSITIVITY DEGRADATION CHARACTERISTICS OF INCORE NEUTRON DETECTOR FOR HEAVY WATER REACTOR,FUGEN NPP

;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

Renovation of chemical processing facility for development of advanced fast reactor fuel cycle system in JNC

; Miyachi, Shigehiko; ;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

The Excellent Fuel Cycle Technology in Nuclear Proliferation Resistace

; Ojima, Hisao; ;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

Feasibility study on nitrogen-15 enrichment and recycling system for innovative FR cycle system with nitride fuel

; Ono, Kiyoshi; ; Sato, Koji;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

DEVELOPMENT OF THE SYSTEM BASED CODE FOR FAST BREEDER REACTORS - PROBABUILISTIC METHODS IN CREEP-FATIGUE EVALUTION -

; Kawasaki, Nobuchika; Morishita, Masaki;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

Development of computer program for whole core thermal-hydraulic analysis of fast reactors

Ohshima, Hiroyuki;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

Journal Articles

None

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), , 

None

Journal Articles

None

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), , 

None

Journal Articles

None

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), , 

None

Journal Articles

None

Passala;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), , 

None

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