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Journal Articles

A ROSA-V experimental study on PWR accident management actions and role of reactor instrumentation

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

Nihon Kikai Gakkai 2005-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.223 - 224, 2005/09

Shown below are experimental results on characteristics of reactor instrumentations including a coolant mass tracking method and core exit thermocouples (CETs) which are necessary to precise operator actions for accident management (AM) during a loss-of-coolant accident (LOCA) at a pressurized water reactor (PWR). The experiments at the ROSA-V/LSTF facility of the Japan Atomic Energy Research Institute simulated small break LOCAs at the PWR vessel bottom and clarified effects of secondary depressurization as one of the AM measures in case of high pressure injection system failure and non-condensable gas inflow from the accumulator injection system. It was shown that the coolant mass tracking method based on three types of water level instruments could detect most of the primary coolant mass change between the initial state and core-heatup starting condition. The CET characteristics to detect the core heatup conditions were significantly degraded by the condensed water fall-back during the secondary depressurization action.

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

Thermal-hydraulic responses during PWR pressure vessel upper head small break LOCA based on LSTF experiment and analysis

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

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 8 Pages, 2005/05

no abstracts in English

Journal Articles

Study of accident management measures for prevention of severe core damage in ROSA-V program

Asaka, Hideaki; Anoda, Yoshinari

Konsoryu, 17(2), p.116 - 125, 2003/06

no abstracts in English

JAEA Reports

Journal Articles

Multi-dimensional thermal-hydraulic analysis for horizontal type PCCS

Arai, Kenji*; Kurita, Tomohisa*; Nakamaru, Mikihide*; Fujiki, Yasunobu*; Nakamura, Hideo; Kondo, Masaya; Obata, Hiroyuki*; Shimada, Rumi*; Yamaguchi, Ken*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

Journal Articles

Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses

Asaka, Hideaki; Anoda, Yoshinari; Kukita, Yutaka*;

Journal of Nuclear Science and Technology, 35(12), p.905 - 915, 1998/12

 Times Cited Count:15 Percentile:76.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments

Yonomoto, Taisuke; Kukita, Yutaka; R.R.Schultz*

Nuclear Technology, 124(1), p.18 - 30, 1998/10

 Times Cited Count:36 Percentile:92.4(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core liquid level responses due to secondary-side depressurization during PWR small break LOCA

Asaka, Hideaki; ; Anoda, Yoshinari; Onuki, Akira; Kukita, Yutaka*

Journal of Nuclear Science and Technology, 35(2), p.113 - 119, 1998/02

 Times Cited Count:10 Percentile:65.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal-hydraulic research on passive safety systems for next-generation PWRs using ROSA/LSTF

Yonomoto, Taisuke

NUREG/CP-0166, 3, p.31 - 52, 1998/00

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following sblocas with totally failed HPI

*; Kukita, Yutaka*; Asaka, Hideaki; M.Wang*; Otani, Etsuo*

Nuclear Technology, 126(3), p.331 - 339, 1998/00

 Times Cited Count:9 Percentile:58.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ROSA-AP600 Experiment simulating a steam generator tube rupture transient

Nakamura, Hideo; Kukita, Yutaka; L.S.Ghan*; R.R.Schultz*

Proc. of 1997 Int. Meeting on Advanced Reactors Safety, 0, p.1245 - 1252, 1997/06

no abstracts in English

Journal Articles

Small break LOCA tests at ROSA-V/LSTF on next generation PWR designs

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

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 1, p.535 - 542, 1997/00

no abstracts in English

Journal Articles

Cold leg one inch break LOCA experiment for the ROSA-AP600 project

Yonomoto, Taisuke; R.Shaw*; Kukita, Yutaka

3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE), 2, p.1053 - 1058, 1995/00

no abstracts in English

Journal Articles

ROSA/AP600 testing: Facility modifications and initial test results

Kukita, Yutaka; Yonomoto, Taisuke; ; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; T.J.Boucher*; M.G.Ortiz*; R.A.Shaw*; R.R.Schultz*

NUREG/CP-0140 (Vol. 2), 0, p.203 - 216, 1995/00

no abstracts in English

Journal Articles

Integral testing on thermal-hydroulic responces of advanced passive-safety PWR AP600

Anoda, Yoshinari; Kukita, Yutaka; Yonomoto, Taisuke; ; Nakamura, Hideo; Kumamaru, Hiroshige; T.J.Boucher*; M.G.Ortiz*; R.A.Shaw*; R.R.Schultz*

Nihon Kikai Gakkai Dai-72-Ki Tsujo Sokai Koenkai Koen Rombunshu, III, 0, p.413 - 414, 1995/00

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF tests on intentional primary system depressurization following PWR small-break LOCA

Kumamaru, Hiroshige; ; M.Wang*; Kukita, Yutaka

Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, p.129 - 136, 1995/00

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

Real-time graphic display system for ROSA-V Large Scale Test Facility

; *; Anoda, Yoshinari; Osaki, Hideki; Kukita, Yutaka

JAERI-M 93-221, 131 Pages, 1993/11

JAERI-M-93-221.pdf:3.5MB

no abstracts in English

24 (Records 1-20 displayed on this page)