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JAEA Reports

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Moribe, Takeshi; ; ;

JNC TY9400 2002-008, 150 Pages, 2002/06

JNC-TY9400-2002-008.pdf:7.26MB

no abstracts in English

JAEA Reports

Design study on gas cooled FBR using coated particle fuel

; ; Kida, Masanori; ; ; ; Hayashi, Hideyuki

JNC TN9400 2001-073, 414 Pages, 2001/06

JNC-TN9400-2001-073.pdf:10.15MB

The phase I feasibility studies on commercialized fast reactor cycle system was conducted until FY2000. In the phase I study, the preliminary designs of the three gas cooled FBR concepts expected to have competitive cost performance with LWR were investigated. The three concepts are (1)Carbon dioxide cooled FBR using pin type fuel, (2)Helium cooled FBR using pin type fuel, (3)Helium cooled FBR using coated particle fuel. This report summarizes the results of the preliminary design study on helium cooled FBR using coated particle fuel conducted until March 2001. The helium cooled FBR plant accomplishes direct gas turbine cycle of high efficiency using heat resisted coated particle fuel and reactor inner structures. The plant also performs core melt proof concept by high temperature performance, negative Doppler coefficient and natural circulation cooling. The plant pursues safety and cost effective concept by the removal of CDA countermeasures, high plant efficiency and realistic twin plant design with modularization. The results have shown that the plant has the possibility of core melt proof safety although the core performance is not sufficient. The plant construction cost is thought to be a little higher than the expected cost and has the possibility to reach the target. The future R&D especially for coated particle fuel and fuel assembly is necessary.

Journal Articles

Feasibility Studies on Commercialized Fast Breeder Reactor System (2)Gas -Cooled High Temperature FBR

; ; Kida, Masanori;

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 534 Pages, 2001/00

None

JAEA Reports

Studies on gas cooled fast breeder reactor results

Ogo, Hideyasu; ; ; ;

JNC TN9400 2000-073, 78 Pages, 2000/06

JNC-TN9400-2000-073.pdf:2.32MB

ln the feasibility studies on commercialized fast reactor cycle system started in July 1999, according to a medium and long-term R&D project and management plan of JNC, various candidate concepts for a fast reactor cycle system are investigated to have good cost performance competitive with LWR system and the related R&D progTams, ln this report candidate fast reactor concepts using various coolants are studied and the related R&D items are picked up, Three concepts of the gas cooled reactor have been selected as follows. (A)Carbon dioxide cooled reactor using fuel pin (B)Helium cooled reactor using fuel pin (C)Helium cooled reactor using coated fuel particles Concept (A) and (C) have been studied concerning the following items in FY1999. (1)Basic specifications (2)Conceptual design of core and fuel (3)Conceptual design of major components (4)Safety design and analysis (5)Countermeasures against core disruptive accidents (6)Reprocessing procedures of coated fuel particles The result of the investigation revealed that the following issues have to be solved in order to realize each concept. For concept (A); how to take counter measures against recriticality from the viewpoint of core performance, feasibility of debris tray (core catcher) to retain molten fuel in coolable and subcritical geometry and development of a large scale gas circulator, etc. For concept (C); development of coated fuel particles, fuel subassemblies, and a helium gas turbin, etc.

Journal Articles

Fuel temperature analysis method for channel-blockage accident in HTTR

Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Kiso, Yoshihiro*; *

Nucl. Eng. Des., 150, p.69 - 80, 1994/00

 Times Cited Count:5 Percentile:47.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Verification of in-core thermal and hydraulic analysis code FLOWNET/TRUMP for the High Temperature Engineering Test Reactor(HTTR) at JAERI

Maruyama, So; Sudo, Yukio; Saito, Shinzo; Kiso, Yoshihiro*; *

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.227 - 232, 1989/12

no abstracts in English

JAEA Reports

Verification of combined thermal-hydraulic and heat conduction analysis code FLOWNET/TRUMP

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Sudo, Yukio

JAERI-M 88-173, 76 Pages, 1988/09

JAERI-M-88-173.pdf:1.78MB

no abstracts in English

JAEA Reports

Disign and evaluation of core flow distribution in High Temperature Engineering Test Reactor(HTTR)

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Takikawa, Noboru*; *; Sudo, Yukio

JAERI-M 88-154, 147 Pages, 1988/08

JAERI-M-88-154.pdf:2.9MB

no abstracts in English

JAEA Reports

Verification of in-vessel thermal and hydraulic analysis code "FLOWNET"

Maruyama, So; Murakami, Tomoyuki*; Kiso, Yoshihiro*; Sudo, Yukio

JAERI-M 88-138, 39 Pages, 1988/07

JAERI-M-88-138.pdf:1.03MB

no abstracts in English

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