Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 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

Study on dryout and rewetting during accidents including ATWS for the BWR at JAEA

Satou, Akira; Wada, Yuki; Shibamoto, Yasuteru; Yonomoto, Taisuke

Nuclear Engineering and Design, 354, p.110164_1 - 110164_10, 2019/12

 Times Cited Count:8 Percentile:66.68(Nuclear Science & Technology)

JAEA has conducted a series of experimental researches on the Post-boiling transition heat transfer, transient critical heat flux and rewetting for BWRs. Experimental data bases covering the anticipated operational conditions was developed; the significance of the precursor cooling was identified. This paper presents approaches of the present research focusing on the anticipated transient without scram, effects of the spacer and physical understanding of the phenomena for development of mechanistic model together with promising results obtained so far.

Journal Articles

Observation of dry patch behavior on copper heat transfer surface and measurement of surface temperature distribution in nucleate pool boiling

Uesawa, Shinichiro; Ono, Ayako; Koizumi, Yasuo; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Dai-55-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 8 Pages, 2018/05

no abstracts in English

JAEA Reports

None

Matsumoto, Mitsuo; ;

PNC TN1410 98-005, 96 Pages, 1998/03

PNC-TN1410-98-005.pdf:2.17MB

no abstracts in English

JAEA Reports

Natural circulation flow analysis of middle size ATR

*; *

PNC TJ9381 94-001, 84 Pages, 1994/02

PNC-TJ9381-94-001.pdf:1.6MB

The study in last year examined the realization of 1000MWt natural circulation ATR. In this study. The sensitivity analysis is did making for the design. The results are as below. (1)The influence of riser pipe diameter. The natural circulation on riser pipe 3B is analyzed. 3B pipe is cheaper than 5B riser pipe that is a base condition. The results are that fuel dryout is happen by 1.8MW channel power on 3B, but is not happen on 5B riser pipe. (2)The influence of the riser pipe number reduction and the riser pipe diameter change. The case of connection 2 pressure tubes by Y piece pipe is analyzed. In this case, the riser pipe number is half. The cases that riser pipe is 5B and 4B are analyzed. The results are as below. (a)Natural circulation flow lower by riser pipe number is half. (b)Fuel dryout is happen by 1.8MW channel power on 4B, but is not happen on 5B. (3)The influence of the middle position header connection and the riser pipe diameter change, The case of connection 50 pressure tubes by the middle position header is analysed. The cases that riser pipe is 24B and 32B are analyzed. The results are as below. (a)In 2 cases, natural circulation flow lower as compared with base case. (b)In 2 cases, fuel dryout are not happen by 1.8MW channel power. (4)The influence of pressure tube diameter. The case of pressure tube diameter widening is analyzed. So, the pressure loss of pressure tube domain govern the flow. (a)Natural circulation flow increase by pressure tube diameter widening. (b)The flow swing is by pressure tube diameter widening. (c)In analysis cases, fuel dryout is not happen. We get 1.8MW channel power on the condition that riser pipe is 4B, riser pipe is connected by Y piece pipe, pressure tube diameter is 122.0mm.

JAEA Reports

Development of degraded core coolability analysis program

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

JAERI-M 89-048, 58 Pages, 1989/05

JAERI-M-89-048.pdf:1.32MB

no abstracts in English

Journal Articles

Effect of gravity-fed water from a downcomer on coolability of a debris bed

Yamano, Norihiro; Maruyama, Yu; Abe, Yutaka; Soda, Kunihisa

AIChE Symp.Ser., 83(257), p.341 - 346, 1987/00

Experiments to investigate the effect of coolant injection from the bottom of a devris bed have been performed, and an analytical model has been developed.

Oral presentation

Assessment of core status of TEPCO's Fukushima Daiichi Nuclear Power Plants, 109; Difference in core energy in core material relocation in Units 2 and 3 of FDNPS and its effects

Sato, Ikken; Yamashita, Takuya; Yoshikawa, Shinji; Li, X.; Pellegrini, M.*; Yamaji, Akifumi*; Kojima, Yoshihiro*

no journal, , 

Difference in core energy between Unit 2 and Unit 3 is evaluated and its effects on coolability of debris relocated to lower plenum and debris-relocation behavior to pedestal are discussed.

7 (Records 1-7 displayed on this page)
  • 1