Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

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

Journal Articles

Containment pressure suppression system with functions of water injection and noncondensable gas confinement

Yonomoto, Taisuke; Okubo, Tsutomu; Iwamura, Takamichi; Ishida, Toshihisa

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 8 Pages, 2003/04

An innovative concept of the pressure suppression system having functions of water injection and non-condensable gas confinement is developed for the next generation light water reactors (LWRs). The use of the system is advantageous for the mitigation of effects of the loss-of-coolant accidents (LOCAs) in (1) keeping the containment pressure as low as for the conventional LWRs, (2) injecting water to the containment for cooling the reactor pressure vessel (RPV) and/or flooding a break, and (3) confining the non-condensable gas in the drywell. The gas confinement function makes the system considerably suitable for reactor designs with passive cooling systems utilizing heat exchangers, such as the steam generator (SG) secondary side cooling system for an integral reactor, and the passive containment cooling system (PCCS), because it avoids adverse effects of non-condensable gas on the heat transfer performance during LOCAs. The usefulness of the developed concept is confirmed in the RELAP5/MOD3 code calculation.

Journal Articles

Loss of Residual Heat Removal(RHR) event during PWR mid-loop operation; ROSA-IV/LSTF experiment without opening on primary loop pressure boundary

Nakamura, Hideo; Katayama, Jiro; Kukita, Yutaka

Power Plant Transients,1992; FED-Vol. 140, p.9 - 16, 1993/00

no abstracts in English

Journal Articles

RELAP5 code analysis of a ROSA-IV/LSTF experiment simulating a loss of residual heat removal event during PWR mid-loop operation

Nakamura, Hideo; Katayama, Jiro; Kukita, Yutaka

Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5,Vol. 5, p.1333 - 1340, 1992/00

no abstracts in English

Journal Articles

The Noncondensable gas effects on loss-of-coolant accident steam condensation loads in BWR pressure suppression pool

; ; ;

Nuclear Technology, 63, p.337 - 346, 1983/00

 Times Cited Count:12 Percentile:77.07(Nuclear Science & Technology)

no abstracts in English

4 (Records 1-4 displayed on this page)
  • 1