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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.
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.
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
Asaka, Hideaki; Anoda, Yoshinari
Konsoryu, 17(2), p.116 - 125, 2003/06
no abstracts in English
ROSA-V Group
JAERI-Tech 2003-037, 479 Pages, 2003/03
JAERI-Tech-2003-037.pdf:19.25MB
no abstracts in English
Suzuki, Mitsuhiro
JAERI-Tech 2002-071, 171 Pages, 2002/10
JAERI-Tech-2002-071.pdf:11.26MB
no abstracts in English
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
Asaka, Hideaki; Anoda, Yoshinari; Kukita, Yutaka*;
Journal of Nuclear Science and Technology, 35(12), p.905 - 915, 1998/12
Times Cited Count：15 Percentile：74.74(Nuclear Science & Technology)no abstracts in English
Yonomoto, Taisuke; Kukita, Yutaka; R.R.Schultz*
Nuclear Technology, 124(1), p.18 - 30, 1998/10
Times Cited Count：40 Percentile：92.81(Nuclear Science & Technology)no abstracts in English
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：63.58(Nuclear Science & Technology)no abstracts in English
Yonomoto, Taisuke
NUREG/CP-0166, 3, p.31 - 52, 1998/00
no abstracts in English
*; Kukita, Yutaka*; Asaka, Hideaki; M.Wang*; Otani, Etsuo*
Nuclear Technology, 126(3), p.331 - 339, 1998/00
Times Cited Count：9 Percentile：57.16(Nuclear Science & Technology)no abstracts in English
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
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
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
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
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
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
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
; *; Anoda, Yoshinari; Osaki, Hideki; Kukita, Yutaka
JAERI-M 93-221, 131 Pages, 1993/11
no abstracts in English
