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Journal Articles

Operation scenarios and requirements for fuel processing in future fusion reactor facilities; Hydrogen isotope separation as a key process for fuel recycle and safety

Ohira, Shigeru; Yamanishi, Toshihiko; Hayashi, Takumi

Journal of Nuclear Science and Technology, 43(4), p.354 - 360, 2006/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

In this paper, expected operation scenarios for ITER and future fusion reactors from a viewpoint of an integrated isotope processing in a future D-T fusion rector are provided with comparisons of requirements for system design attributed to the operation scenarios, safety requirements, etc. Most of the basic requirements for fuel process of a D-T fusion reactor facility common are the same, but the design requirements coming from the individual operation scenarios of ITER and future demo reactors will differ. The system design requirements of the tritium plant taking care of various operations of ITER and a demo reactor are examined and compared. Due to the increase of tritium concentration in the coolant of a demo reactor by tritium permeation in the structural material of the in-vessel components operated at a temperature higher than that of ITER detritiation of coolant will be getting more important. Some important key parameters related to hydrogen isotope processing in future fusion reactors will be discussed.

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

Status of lithium target system for International Fusion Material Irradiation Facility (IFMIF)

Nakamura, Hiroo; Ida, Mizuho*; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki*; IFMIF International Team

Fusion Engineering and Design, 58-59, p.919 - 923, 2001/11

 Times Cited Count:9 Percentile:56.08(Nuclear Science & Technology)

no abstracts in English

Journal Articles

System design of a superconducting linac for the high-intensity proton accelerator project

Hasegawa, Kazuo; Ouchi, Nobuo; Mukugi, Ken*

KEK Proceedings 2000-23, p.31 - 33, 2001/02

no abstracts in English

Journal Articles

Design analysis on the magnetic field control system in compact ITER

Senda, Ikuo; Shoji, Teruaki; Araki, Masanori; ITER Japan Home Team; ITER Joint Central Team

International Journal of Applied Electromagnetics and Mechanics, 13(1-4), p.349 - 357, 2001/00

no abstracts in English

Journal Articles

System design of a superconducting linac for the JAERI-KEK joint project

Hasegawa, Kazuo; Mizumoto, Motoharu; Ouchi, Nobuo; Noguchi, Shuichi*

KEK Proceedings 99-25, p.28 - 32, 2000/02

no abstracts in English

Journal Articles

Development of superconducting linac for the KEK/JAERI joint project

Ouchi, Nobuo; Mizumoto, Motoharu; Kusano, Joichi; Chishiro, Etsuji; Hasegawa, Kazuo; Akaoka, Nobuo*; Saito, Kenji*; Noguchi, Shuichi*; Kako, Eiji*; Inoue, Hitoshi*; et al.

Proceedings of 20th International Linac Conference (CD-ROM), 1 Pages, 2000/00

no abstracts in English

JAEA Reports

Operation system concept for high-level radioactive wastes disposal facility

*; *; Tanai, Kenji

JNC TN8400 99-050, 94 Pages, 1999/11

JNC-TN8400-99-050.pdf:3.86MB

This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.

JAEA Reports

Aerodynamic design study on HTGR helium gas turbines; Investigation on the effect of design conditions

*; ; Ishiyama, Shintaro

JAERI-Tech 99-016, 155 Pages, 1999/03

JAERI-Tech-99-016.pdf:5.86MB

no abstracts in English

JAEA Reports

None

JNC TJ1400 99-004, 110 Pages, 1999/02

JNC-TJ1400-99-004.pdf:2.42MB

no abstracts in English

JAEA Reports

The Development of Radiation Hardened Microcomputer System; System Design

Ishibashi, Yuzo; Kuroda, Yoshikatsu*; Nakajima, Atsushi*

PNC TJ8216 98-003, 243 Pages, 1998/03

PNC-TJ8216-98-003.pdf:6.5MB

no abstracts in English

JAEA Reports

None

Kubota, Shigeru*; *; Okutsu, Kazuo*; Horita, M.*; Amemiya, Kiyoshi*

PNC TJ1449 98-001, 1944 Pages, 1998/02

PNC-TJ1449-98-001.pdf:76.65MB

None

Journal Articles

Status of the high intensity proton accelerator development at JAERI

Hasegawa, Kazuo; Mizumoto, Motoharu; Kusano, Joichi; Tomisawa, Tetsuo; Ouchi, Nobuo; Oguri, Hidetomo; Kinsho, Michikazu; Touchi, Y.*; Honda, Yoichiro*; Akaoka, Nobuo*; et al.

Proceedings of 23rd Linear Accelerator Meeting in Japan, p.19 - 21, 1998/00

no abstracts in English

JAEA Reports

None

PNC TJ8164 97-003, 77 Pages, 1997/03

PNC-TJ8164-97-003.pdf:6.5MB

no abstracts in English

JAEA Reports

None

*; *

PNC TJ1211 97-001, 820 Pages, 1997/01

PNC-TJ1211-97-001.pdf:22.65MB

None

JAEA Reports

None

*; *; *; *; *; Tanaka, Tatsuya*

PNC TJ1201 96-001, 288 Pages, 1996/02

PNC-TJ1201-96-001.pdf:49.37MB

None

JAEA Reports

None

*; *; *; *; *

PNC TJ1678 95-002, 121 Pages, 1995/02

PNC-TJ1678-95-002.pdf:4.83MB

None

JAEA Reports

Conceptual design study of fast reactor system for deep sea research submersible

; Haga, Kazuo

PNC TN9410 92-050, 71 Pages, 1992/02

PNC-TN9410-92-050.pdf:1.26MB

Objective : A conceptual design of a fast reactor system was studied for deep sea research submersibles diving to the maximum depthes of 10,924m and 8,000m. Method : A space reactor concept was used for the system. Primary coolant of the system was NaK, whose temperatures was set as 680 and 550 $$^{circ}$$C at the exit of a reactor vessel. Secondary system was a closed brayton xcycle using He(60)-Xe(40) gas as working fluid. Electric power output was 20kWe. Thermal efficiency, transported thermal energy, and flow rates and temperatures of the gas and NaK were calculated at closed Brayton cycle analyses. Results : The conceptual design was drawn, based on the size of an each component fixed with the calculated results of these values. The system could be set in a pressure hull comprising of a 2.3m$$^{10}$$ shere and a 1.1m $$^{10}$$ pipe. A simple figure was drawn of the research submersible loading the system. The whole length of the submersible was about 14m. Its weights were about 100ton and 70ton for the maximum depthes of 10,924m and 8,000m respectively. It could be carried by a nother ship. Conclusion : The submersible had the following features compared with the one loading electric cells on account of affluent electric power generation by the fast reactor system. A continuous stay longer than a week and movement at a high speed were made possible over a deep sea bottom. An illuminated region was very wide during sea bottom survey. Observation by watching was possible over a wide region. Therefore the submersible could be considered to be used for detail observation over crackes in the Japan trench and etc.

18 (Records 1-18 displayed on this page)
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