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Journal Articles

Status of investigation to ensure applicability of ECCS acceptance criteria to high-burnup fuel

Ozawa, Masaaki*; Amaya, Masaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(4), p.185 - 200, 2020/12

no abstracts in English

JAEA Reports

Investigation of molten salt fast breeder reactor

; ; ; ;

JNC TN9400 2000-066, 52 Pages, 2000/06

JNC-TN9400-2000-066.pdf:1.82MB

Phase I of feasibility studies on commercialized fast reactor system is being peformed for two years from Japanese Fiscal Year 1999. In this report, results of the study on fluid fuel reactors (especialiy a molten salt fast breeder reactor concept) are described from the viewpoint of technical and economical concerns of the plant system design. ln JFY1999, we have started to investigate the fluid fuel reactors as alternative concepts of sodium cooled FBR systems with MOX fuel, and selected the unique concept of a molten chloride fast, breeder reactor, whose U-Pu fuel cycle can be related to both light water reactors and fast breeder reactors on the basis of present technical data and design experiences. We selected a preliminary composition of molten fuel and conceptual plant design through evaluation of technical and economical issues essential for the molten salt reactors and then compared them with reference design concepts of sodium cooled FBR systems under limited information on the molten chloride fast breeder reactors. The following results were obtained. (1)The molten chloride fast breeder reactors have inherent safety features in the core and plant performances, ad the fluid fuel is quite promising for cost reduction of the fuel fabrication and reprocessing. (2)On the other hand, the inventory of the molten chloride fuel becomes high and thermal conductivity of the coolant is inferior compared to those of sodium cooled FBR systems, then, the size of main components such as lHX's becomes larger and the amount of construction materials is seems to be increased. (3)Furthermore economical vessel and piping materials which contact with the molten chloride salts are required to be developed. From the results, it is concluded that further steps to investigate the molten chloride fast breeder reactor concepts are too early to be conducted.

Journal Articles

Estimation of reactor pool water temperature after shutdown in JRR-3M

; Sato, Mitzugu;

JAERI-Conf 99-006, p.136 - 141, 1999/08

no abstracts in English

Journal Articles

Confirmatory testing on the AP600 passive reactor design

Anoda, Yoshinari

Genshiryoku Shisutemu Nyusu, 10(1), p.12 - 18, 1999/00

no abstracts in English

JAEA Reports

Study on thermal-hydraulics during a PWR reflood phase

Iguchi, Tadashi

JAERI-Research 98-054, 216 Pages, 1998/10

JAERI-Research-98-054.pdf:7.94MB

no abstracts in English

Journal Articles

Study on steam explosion and molten core coolability in ALPHA program

Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; H.S.Park*; Sugimoto, Jun

Proc. of 11th KAIF/KNS Annual Conf., 0, p.827 - 838, 1996/00

no abstracts in English

JAEA Reports

Operation experience report of experimental fast reactor JOYO; Operation expelience of primary main and auxiliary cooling systems of JOYO

Karube, Koji; ; ; ; Kawai, Masashi;

PNC TN9440 93-012, 83 Pages, 1993/04

PNC-TN9440-93-012.pdf:5.27MB

This report describes the operating experience of the primary main cooling system from January 1982 to March 1992, and of the primary auxiliary cooling system from october 1986 to March 1992. 0ut lines of the operating experience ale followings; There have been no serious troubles in this period. (1)The main system; Operation time of the circulation pumps are about 67675 hours. Accumulated operation time of the pumps are about 105970 hours. The pumps has been started 212 times. (2)The auxiliary system; Operation time of the circulation pump (EMP) is about 4767 hours. Accumulated operation time of the pump is about 8667 hours. The pump has been automatically started 31 times with the scheduled test.

Journal Articles

ROSA-IV/LSTF experiment simulating loss-of-residual heat removal; Pressurization mechanism at experiment without opening

Nakamura, Hideo; Katayama, Jiro; Anoda, Yoshinari; Kukita, Yutaka

Nihon Kikai Gakkai Dai-69-Ki Tsujo Sokai Koenkai Koen Rombunshu, Vol.B, p.456 - 458, 1992/00

no abstracts in English

JAEA Reports

Database for the degraded core coolability experiments

Maruyama, Yu; Abe, Yutaka; *; Soda, Kunihisa

JAERI-M 89-054, 142 Pages, 1989/05

JAERI-M-89-054.pdf:3.38MB

no abstracts in English

Journal Articles

An experimental study on PWR-LOCA by ROSA-II, (IV)the severe break configulation in a hot leg break for core cooling during blowdown

; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 20(5), p.347 - 358, 1978/05

 Times Cited Count:0

no abstracts in English

Journal Articles

Experimental study on PWR-LOCA by ROSA-II, (III)

; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 20(3), p.185 - 194, 1978/03

 Times Cited Count:0

no abstracts in English

Oral presentation

Study on molten core coolability under precautionary water injection into containment vessel, 3; Improvement of melt spread model in the JASMINE code

Kawabe, Ryuhei; Matsumoto, Toshinori; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

Oral presentation

Study on molten core coolability under precautionary water injection into containment vessel, 2; Analysis by improved melt spreading model in JASMINE

Kawabe, Ryuhei; Matsumoto, Toshinori; Ajima, Kohei; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

14 (Records 1-14 displayed on this page)
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