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Kim, Y. S.*; Kang, T.*; Hong, S.-K.*; Brechtl, J.*; Lebyodkin, M.*; Cheng, Y.-H.*; Huang, E.-W.*; Liaw, P. K.*; Harjo, S.; Gong, W.; et al.
Acta Materialia, 292, p.120970_1 - 120970_16, 2025/06
Times Cited Count:12 Percentile:93.82(Materials Science, Multidisciplinary)Takeda, Takeshi
JAEA-Data/Code 2023-007, 72 Pages, 2023/07
An experiment denoted as IB-HL-01 was conducted on November 19, 2009 using the Large Scale Test Facility (LSTF) in the Rig of Safety Assessment-V (ROSA-V) Program. The ROSA/LSTF experiment IB-HL-01 simulated a 17% hot leg intermediate break loss-of-coolant accident due to a double-ended guillotine break of pressurizer surge line in a pressurized water reactor (PWR). The break was simulated by a long nozzle upwardly mounted flush with a hot leg inner surface. The test assumptions included total failure of both high pressure injection system of emergency core cooling system (ECCS) and auxiliary feedwater system. In the experiment, relatively large size of break led to a fast transient of phenomena. The primary pressure steeply dropped after the break, and became lower than steam generator (SG) secondary-side pressure. Break flow turned from single-phase flow to two-phase flow soon after the break. Core uncovery started simultaneously with liquid level drop in downflow-side of crossover leg before loop seal clearing (LSC). The LSC was induced in both loops by steam condensation on accumulator (ACC) coolant of ECCS injected into cold legs. The whole core was quenched owing to the rapid recovery in the core liquid level after the LSC. Peak cladding temperature of simulated fuel rods was detected almost concurrently with the LSC. During the ACC coolant injection, liquid levels recovered in the hot legs and SG inlet plena because of liquid entrainment from the hot leg into the SG inlet plenum by high-velocity steam flow. After the continuous core cooling was confirmed through the actuation of low pressure injection system of ECCS, the experiment was terminated. This report summarizes the test procedures, conditions, and major observations in the ROSA/LSTF experiment IB-HL-01.
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count:11 Percentile:64.37(Nuclear Science & Technology)Udagawa, Yutaka; Nagase, Fumihisa; Fuketa, Toyoshi
JAERI-Research 2005-020, 40 Pages, 2005/09
In order to investigate effects of quenching temperature and cooling rate before quench on cladding ductility reduction under LOCA conditions, samples cut from non-irradiated 17
17-type Zircaloy-4 cladding tubes for PWRs were oxidized in steam at 1373 and 1473 K, cooled at 2 to 7 K/s, and quenched at 1073 to 1373 K. The quenched samples were subjected to ring compression test, microstructure observation, and Vickers hardness test. Quenching temperature decrease obviously increased area fraction of
phase in the radial cross section of the cladding, and reduced cladding ductility. Slow-cooling rate decrease increased unit size and hardness of precipitated
phase, while
phase area fraction and cladding ductility were not significantly changed.
phase is harder than the surrounding region in the metallic layer and has higher oxygen content, indicating its low ductility. Consequently, increase in the area fraction in the cladding is a main cause of the reduction in cladding ductility with decrease in the quenching temperature.
Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 40(4), p.213 - 219, 2003/04
Times Cited Count:78 Percentile:96.86(Nuclear Science & Technology)Isothermal oxidation tests in flowing steam were performed on low-Sn Zircaloy-4 cladding tubes over the wide temperature range from 773 to 1573 K in order to obtain oxidation kinetics applicable to various loss-of-coolant accident conditions of LWRs. The oxidation generally obeys a parabolic rate law for the examined time range up to 3600s at temperatures from 1273 K to 1573K, and for a limited time range up to 900s from 773 to 1253 K. A cubic rate law is preferable for evaluating the longer-term oxidation at 1253 K and below. The parabolic rate law constant and the cubic rate law constant for measured weight gain were evaluated at every examined temperature, and Arrhenius-type equations were determined in order to describe the temperature dependence of the rate constants. It was indicated that the change of the oxidation kinetics from the cubic to the parabolic rate and the discontinuities in the temperature dependence of the rate constants are caused by the monoclinic/tetragonal phase transformation of ZrO
.
by K-absorption edge XAFSOkamoto, Yoshihiro; Shiwaku, Hideaki; Yaita, Tsuyoshi; Narita, Hirokazu; Tanida, Hajime*
Journal of Molecular Structure, 641(1), p.71 - 76, 2002/10
Times Cited Count:43 Percentile:71.38(Chemistry, Physical)The local structure of molten LaCl
was investigated by X-ray absorption fine structure(XAFS) of the La K-edge. The nearest La
-Cl
distance andcoordination number were 2.89
and 7.4
from the curve fitting of the 1st peak in the fourier transform magnitude
. The coordination number larger than 6 suggests that the local structure of molten LaCl
is not a simple octahedral coordination (LaCl
)
, but 7-fold (LaCl
)
and/or 8-fold (LaCl
)
complexes. The 1st La
-La
distance, of which correlation was observed as a weak 2nd peak in the
, was evaluated to be 4.9
. It suggests that the distorted corner-sharing connection of the complex species is predominant in the melt, inontrast with molten YCl
in which the edge-sharing connection of the 6-fold (YCl
)
mainly exists.
in LiCl-KCl eutecticOkamoto, Yoshihiro; Motohashi, Haruhiko*
Zeitschrift f
r Naturforschung, A, 579(5), p.277 - 280, 2002/05
The local structure of molten ZrCl
in LiCl-KCl eutectic was investigated by using an X-ray absorption fine structure(XAFS) of the Zr K-absorption edge. The nearest Zr
-Cl
distance and coordination number from the curve fitting analysis were 2.51
and 5.8
0.6, respectively. These suggest that a 6-fold coordination (ZrCl
)
is predominant in the mixture melt.
Kumamaru, Hiroshige; Murata, Hideo; ; Kukita, Yutaka
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.217 - 222, 1995/00
no abstracts in English
Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*
Journal of Nuclear Science and Technology, 31(1), p.62 - 72, 1994/01
Times Cited Count:4 Percentile:41.61(Nuclear Science & Technology)no abstracts in English
Jitsukawa, Shiro; Hojo, Kiichi
Journal of Nuclear Materials, 212-215, p.221 - 225, 1994/00
Times Cited Count:9 Percentile:62.46(Materials Science, Multidisciplinary)no abstracts in English
; Koizumi, Yasuo; Tasaka, Kanji
Nucl.Eng.Des., 103, p.239 - 250, 1987/00
Times Cited Count:3 Percentile:37.51(Nuclear Science & Technology)no abstracts in English
;
Journal of the Physical Society of Japan, 55(1), p.193 - 199, 1986/00
Times Cited Count:0 Percentile:0.00(Physics, Multidisciplinary)no abstracts in English
ion irradiation; ; ; ; ;
Proc.XIth Int.Cong.on Electron Microscopy, p.1281 - 1282, 1986/00
no abstracts in English
; ; Murao, Yoshio
JAERI-M 84-026, 77 Pages, 1984/02
no abstracts in English
; ;
Journal of the Physical Society of Japan, 53(12), p.4353 - 4358, 1984/00
Times Cited Count:9 Percentile:64.48(Physics, Multidisciplinary)no abstracts in English
; Murao, Yoshio
Journal of Nuclear Science and Technology, 20(8), p.645 - 657, 1983/08
Times Cited Count:5 Percentile:56.22(Nuclear Science & Technology)no abstracts in English
JAERI-M 83-096, 49 Pages, 1983/07
no abstracts in English
; Hashimoto, Masao; ; ;
JAERI-M 83-083, 68 Pages, 1983/06
no abstracts in English
Hashimoto, Masao; ; ; ;
JAERI-M 83-038, 56 Pages, 1983/03
no abstracts in English
; Murao, Yoshio
JAERI-M 83-026, 118 Pages, 1983/02
no abstracts in English