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Journal Articles

Effects of secondary depressurization on core cooling in PWR vessel bottom small break LOCA experiments with HPI failure and gas inflow

Suzuki, Mitsuhiro; Takeda, Takeshi; Asaka, Hideaki; Nakamura, Hideo

Journal of Nuclear Science and Technology, 43(1), p.55 - 64, 2006/01

 Times Cited Count:10 Percentile:38.8(Nuclear Science & Technology)

Effects of non-condensable gas from the accumulator tanks on secondary depressurization, as one of accident management (AM) measures in case of high pressure injection system failure, are studied at the ROSA-V/LSTF experiments simulating a ten instrument-tube break LOCA at the PWR vessel bottom. In an experiment with no gas inflow, the secondary depressurization at -55 K/h initiated by SI signal with 10 minutes delay succeeded in the LPI actuation. On the other hand, the gas inflow in another experiment degraded the primary depressurization and resulted in core uncovery before the LPI start. The third experiment with rapid secondary depressurization and continuous auxiliary feedwater supply, however, showed a possibility of long-term core cooling by the LPI actuation. RELAP5/MOD3 code analyses well predicted these experiment results and clarified that condensation heat transfer was largely degraded by the gas in the U-tubes. In addition, a primary pressure - coolant mass map was found to be useful for indication of key plant parameters of AM measures.

JAEA Reports

Experimental study on secondary depressurization action for PWR vessel bottom small break LOCA with HPI failure and gas inflow (ROSA-V/LSTF test SB-PV-03)

Suzuki, Mitsuhiro; Takeda, Takeshi; Asaka, Hideaki; Nakamura, Hideo

JAERI-Research 2005-014, 170 Pages, 2005/06

JAERI-Research-2005-014.pdf:7.64MB

A small break LOCA (SBLOCA) experiment was conducted at the LSTF of ROSA-V program to study effects of accident management (AM) on core cooling, which is important in case of high pressure injection (HPI) system failure during an SBLOCA at a PWR. The experiment, SB-PV-03, simulated ten instrument-tube break LOCA at the PWR vessel bottom equivalent to 0.2% cold leg break, total HPI failure, non-condensable gas inflow from accumulator injection system (AIS) and AM actions on secondary depressurization at -55 K/h and auxiliary feedwater (AFW) supply for 30 minutes. It was clarified that the AM actions were effective on primary depressurization until AIS injection end at 1.6 MPa, but thereafter became less effective by the gas inflow, resulting in low pressure injection (LPI) delay and whole core heatup under continuous water discharge at the break. The report describes these phenomena including core heatup related with primary coolant mass and AM actions, primary-to-secondary heat transfer analysis and estimation of gas in the primary loops.

Journal Articles

Effects of secondary depressurization on PWR bottom small break LOCA experiments in case of HPI failure and non-condensable gas inflow

Suzuki, Mitsuhiro; Takeda, Takeshi; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 14 Pages, 2004/10

no abstracts in English

Journal Articles

Experimental investigation of thermal-hydraulic performance of PCCS with horizontal tube heat exchangers; Single U-tube test

Nakamura, Hideo; Anoda, Yoshinari; Tabata, Hiroaki*; Obata, Hiroyuki*; Arai, Kenji*; Kurita, Tomohisa*

JAERI-Conf 2000-015, p.177 - 184, 2000/11

no abstracts in English

Journal Articles

Calculation of thermal-hydraulic behavior of horizontal heat exchanger with parallel tubes

Kondo, Masaya; Otani, Etsuo*; Nakamura, Hideo; Asaka, Hideaki*; Anoda, Yoshinari

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.344 - 350, 2000/00

no abstracts in English

Journal Articles

Status and subjects of thermal-hydraulic analysis for next-generation LWRs with passive safety systems

Aritomi, Masanori*; Onuki, Akira; Arai, Kenji*; *; Yonomoto, Taisuke; Araya, Fumimasa; Akimoto, Hajime

Nippon Genshiryoku Gakkai-Shi, 41(7), p.738 - 757, 1999/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Status and subjects of thermal-hydraulic analyses for next-generation LWRs with passive safety system

Onuki, Akira

Dai-1-Kai Oganaizudo Konsoryu Foramu Koen Rombunshu, p.73 - 82, 1997/00

no abstracts in English

Journal Articles

Non-condensable gas effects in ROSA/AP600 small-break LOCA experiments

Nakamura, Hideo; Kukita, Yutaka; R.A.Shaw*; R.R.Schultz*

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART A), p.237 - 244, 1996/00

no abstracts in English

Journal Articles

PWR thermal-hydraulic phenomena following loss of residual heat removal(RHR) during mid-loop operation

Nakamura, Hideo; Kukita, Yutaka

Int. Conf. on New Trends in Nulear System Thermohydraulics,Vol. 1, 0, p.77 - 86, 1994/00

no abstracts in English

Journal Articles

Evaluation of effects of finite mixing time and non-condensable gas on fuel sodium interactions

Journal of Nuclear Science and Technology, 14(6), p.395 - 406, 1977/06

 Times Cited Count:0

no abstracts in English

12 (Records 1-12 displayed on this page)
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