Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 183

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Technical basis of ECCS acceptance criteria for light-water reactors and applicability to high burnup fuel

Nagase, Fumihisa; Narukawa, Takafumi; Amaya, Masaki

JAEA-Review 2020-076, 129 Pages, 2021/03

JAEA-Review-2020-076.pdf:3.9MB

Each light-water reactor (LWR) is equipped with the Emergency Core Cooling System (ECCS) to maintain the coolability of the reactor core and to suppress the release of radioactive fission products to the environment even in a loss-of-coolant accident (LOCA) caused by breaks in the reactor coolant pressure boundary. The acceptance criteria for ECCS have been established in order to evaluate the ECCS performance and confirm the sufficient safety margin in the evaluation. The limits defined in the criteria were determined in 1975 and reviewed based on state-of-the-art knowledge in 1981. Though the fuel burnup extension and necessary improvements of cladding materials and fuel design have been conducted, the criteria have not been reviewed since then. Meanwhile, much technical knowledge has been accumulated regarding the behavior of high-burnup fuel during LOCAs and the applicability of the criteria to the high-burnup fuel. This report provides a comprehensive review of the history and technical bases of the current criteria and summarizes state-of-the-art technical findings regarding the fuel behavior during LOCAs. The applicability of the current criteria to the high-burnup fuel is also discussed.

Journal Articles

Major outcomes through recent ROSA/LSTF experiments and future plans

Takeda, Takeshi; Wada, Yuki; Shibamoto, Yasuteru

World Journal of Nuclear Science and Technology, 11(1), p.17 - 42, 2021/01

Journal Articles

Fuel behavior in a LOCA

Nagase, Fumihisa

Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.148 - 155, 2001/06

no abstracts in English

Journal Articles

A Feasibility study on core cooling of reduced-moderation PWR with tight lattice core

Onuki, Akira; Yoshida, Hiroyuki; Akimoto, Hajime

Proceedings of ANS International Meeting on Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000) (CD-ROM), 17 Pages, 2000/00

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

None

Yamaguchi, Takashi

PNC TN1410 97-029, 65 Pages, 1997/08

PNC-TN1410-97-029.pdf:1.26MB

no abstracts in English

JAEA Reports

None

Yamaguchi, Takashi

PNC TN1410 97-028, 14 Pages, 1997/07

PNC-TN1410-97-028.pdf:0.28MB

no abstracts in English

Journal Articles

Application of PSA methodology to design improvement of JAERI passive safety reactor (JPSR)

Iwamura, Takamichi; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.316 - 326, 1996/04

 Times Cited Count:1 Percentile:14.78(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reactor safety issues resolved by 2D/3D program

JAERI 1336, 362 Pages, 1995/09

JAERI-1336.pdf:15.72MB

no abstracts in English

JAEA Reports

2D/3D program work summary report

JAERI 1335, 376 Pages, 1995/09

JAERI-1335.pdf:16.12MB

no abstracts in English

Journal Articles

Passive safety injection experiments with a large-scale pressurized water reactor simulator

Yonomoto, Taisuke; Kukita, Yutaka; Anoda, Yoshinari;

Nuclear Technology, 109, p.338 - 345, 1995/03

 Times Cited Count:10 Percentile:70.3(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of system thermal hydraulic responses for passive safety injection experiment at ROSA-IV/Large Scale Test Facility using JAERI modified version of RELAP5/MOD2 code

; Yonomoto, Taisuke; Kukita, Yutaka

Journal of Nuclear Science and Technology, 31(12), p.1265 - 1274, 1994/12

 Times Cited Count:3 Percentile:36.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study on difference in reflood core heat transfer among CCTF, FLECHT-SET and predicted with FLECHT correlation

Okubo, Tsutomu; Iguchi, Tadashi; Murao, Yoshio

Journal of Nuclear Science and Technology, 31(8), p.839 - 849, 1994/08

 Times Cited Count:0 Percentile:0.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Terminating core boiling by hot-leg injection in cold-leg small-break LOCA

Kumamaru, Hiroshige; Kukita, Yutaka

Int. Conf. on New Trends in Nuclear System Thermohydraulics,Vol. 1, 0, p.119 - 126, 1994/00

no abstracts in English

Journal Articles

Passive safety injection experiments with a large-scale PWR simulator

Yonomoto, Taisuke; Kukita, Yutaka; Anoda, Yoshinari;

Proc. of ARS 94 Int. Topical Meeting on Advansed Reactors safety, 1, p.216 - 223, 1994/00

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; ; ; ; ;

PNC TN9440 93-012, 83 Pages, 1993/04

PNC-TN9440-93-012.pdf:2.16MB

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

Quasi-static core liquid level depression and long-term core uncovery during a PWR LOCA

Kukita, Yutaka; R.R.Schultz*; Nakamura, Hideo; Katayama, Jiro*

Nucl. Saf., 34(1), p.33 - 48, 1993/01

no abstracts in English

Journal Articles

RELAP5 analysis of a gravity-driven injection experiment at ROSA-V/Large Scale Test Facility

Yonomoto, Taisuke; Kukita, Yutaka

Proc. on the ASME Winter Annual Meeting, 8 Pages, 1993/00

no abstracts in English

JAEA Reports

Study on the safety of an large scale fast breeder reactor

; ; ;

PNC TN9410 92-068, 73 Pages, 1992/03

PNC-TN9410-92-068.pdf:2.12MB

ln order to be useful for selecting specifications about the safety of the large scale fast breeder rector on and after Monju, following items were studied. (1)Design conditions of the reactor containment, (2)scenarios as to evaluation of core disruptive accident, and (3)applicability of the method of PSA. Technical documents provided for these studies are su㎜arized in this report.

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-15(Run 75); Investigation of FLECHT-SET coupling test results

Okubo, Tsutomu; Iguchi, Tadashi; ; Murao, Yoshio

JAERI-M 91-227, 89 Pages, 1992/01

JAERI-M-91-227.pdf:1.82MB

no abstracts in English

183 (Records 1-20 displayed on this page)