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Journal Articles

Fundamental mechanisms of discontinuous deformation in metals for cryogenic-environment applications

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)

JAEA Reports

Data report of ROSA/LSTF experiment IB-HL-01; 17% hot leg intermediate break LOCA with totally-failed high pressure injection system

Takeda, Takeshi

JAEA-Data/Code 2023-007, 72 Pages, 2023/07

JAEA-Data-Code-2023-007.pdf:3.24MB

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.

Journal Articles

The Effect of azimuthal temperature distribution on the ballooning and rupture behavior of Zircaloy-4 cladding tube under transient-heating conditions

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)

JAEA Reports

Effects of temperature history during cooling process on cladding ductility reduction under lost of coolant accident conditions

Udagawa, Yutaka; Nagase, Fumihisa; Fuketa, Toyoshi

JAERI-Research 2005-020, 40 Pages, 2005/09

JAERI-Research-2005-020.pdf:4.63MB

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$$times$$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 $$alpha$$ phase in the radial cross section of the cladding, and reduced cladding ductility. Slow-cooling rate decrease increased unit size and hardness of precipitated $$alpha$$ phase, while $$alpha$$ phase area fraction and cladding ductility were not significantly changed. $$alpha$$ 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.

Journal Articles

Oxidation kinetics of low-Sn Zircaloy-4 at the temperature range from 773 to 1573 K

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$$_{2}$$.

Journal Articles

Local structure of molten LaCl$$_3$$ by K-absorption edge XAFS

Okamoto, 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$$_3$$ was investigated by X-ray absorption fine structure(XAFS) of the La K-edge. The nearest La$$^{3+}$$-Cl$$^-$$ distance andcoordination number were 2.89$$pm0.01$$${AA}$ and 7.4$$pm0.5$$ from the curve fitting of the 1st peak in the fourier transform magnitude $$|FT|$$. The coordination number larger than 6 suggests that the local structure of molten LaCl$$_3$$ is not a simple octahedral coordination (LaCl$$_6$$)$$^{3-}$$, but 7-fold (LaCl$$_7$$)$$^{4-}$$ and/or 8-fold (LaCl$$_8$$)$$^{5-}$$ complexes. The 1st La$$^{3+}$$-La$$^{3+}$$ distance, of which correlation was observed as a weak 2nd peak in the $$|FT|$$, was evaluated to be 4.9${AA}$. It suggests that the distorted corner-sharing connection of the complex species is predominant in the melt, inontrast with molten YCl$$_3$$ in which the edge-sharing connection of the 6-fold (YCl$$_6$$)$$^{3-}$$ mainly exists.

Journal Articles

XAFS study of molten ZrCl$$_4$$ in LiCl-KCl eutectic

Okamoto, Yoshihiro; Motohashi, Haruhiko*

Zeitschrift f$"u$r Naturforschung, A, 579(5), p.277 - 280, 2002/05

The local structure of molten ZrCl$$_4$$ in LiCl-KCl eutectic was investigated by using an X-ray absorption fine structure(XAFS) of the Zr K-absorption edge. The nearest Zr$$^{4+}$$-Cl$$^-$$ distance and coordination number from the curve fitting analysis were 2.51$$pm0.02AA$$ and 5.8$$pm$$0.6, respectively. These suggest that a 6-fold coordination (ZrCl$$_6$$)$$^{2-}$$ is predominant in the mixture melt.

Journal Articles

Measurement of local void fraction distribution in rod bundle under high-pressure high-temperature boil-off conditions by using optical void probe

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

Journal Articles

Evaluation of local power distribution with fine-mesh core model for High Temperature Engineering Test Reactor(HTTR)

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

Journal Articles

Effect of temperature and flux change on the behavior of radiation induced dislocation loops in pure aluminum

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

Journal Articles

Core heat transfer analysis during a BWR LOCA simulation experiment at ROSA-III

; 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 Articles

A Study of defect structures in fast neutron irradiated nickel at low temperature using magnetic anisotropy measurements

;

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

Journal Articles

Observation of defect clusters in masked thin foil CU by He$$^{+}$$ ion irradiation

; ; ; ; ;

Proc.XIth Int.Cong.on Electron Microscopy, p.1281 - 1282, 1986/00

no abstracts in English

JAEA Reports

Journal Articles

Point defects and induced magnetic anisotropy in fast neutron irradiated iron

; ;

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

Journal Articles

Experimental study of effect of initial clad temperature on reflood phenomena during PWR-LOCA

; 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

JAEA Reports

JAEA Reports

Multi-Rod Burst Test Under a Loss-of-Coolant Accident Condition,3; Experimental Resalt of the Bundle No.7807

Hashimoto, Masao; ; ; ;

JAERI-M 83-038, 56 Pages, 1983/03

JAERI-M-83-038.pdf:2.8MB

no abstracts in English

35 (Records 1-20 displayed on this page)