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Journal Articles

Simulation of quench tests of the central solenoid insert coil in the ITER central solenoid model coil

Takahashi, Yoshikazu; Yoshida, Kiyoshi; Nabara, Yoshihiro; Edaya, Masahiro*; Mitchell, N.*

IEEE Transactions on Applied Superconductivity, 16(2), p.783 - 786, 2006/06

 Times Cited Count:9 Percentile:46.22(Engineering, Electrical & Electronic)

To investigate the conductor behavior during a quench, quench tests of Center Solenoid (CS) insert coils were carried out with various initial conditions in DC and pulse modes. The conductor has very similar configuration and parameters. The inductive heater, attached at the center of the length, initiated an artificial quench in DC mode. A quench has also occurred during the pulse operation with the ramping rate of 0.4-2 T/s. Simulations of electric, thermal and hydraulic behaviors of the conductor during the quench tests in both modes were carried out by using the thermohydraulic simulation code. The experimental results were compared with the simulation and good agreement was obtained. These results are described and the implication for quench detection in ITER is discussed in this paper. The voltage tap method will be used for the quench detection for the CS, and the sensitivity of the detection and the maximum temperature of the conductor during a quench are described. It is shown that the detection system could be designed with high enough detection sensitivity.

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

Quench detection using pick-up coils for the ITER Central Solenoid

Takahashi, Yoshikazu; Yoshida, Kiyoshi; Mitchell, N.*

IEEE Transactions on Applied Superconductivity, 15(2), p.1395 - 1398, 2005/06

 Times Cited Count:8 Percentile:43.27(Engineering, Electrical & Electronic)

The quench detection is important and necessary for the coil protection. The voltage tape method and the flow meter method are both considered for the ITER Central Solenoid (CS). The voltage tap method is primary due to its quick response. The CS consists of six pancake wound modules, which are operated with individual operating current patterns in ac mode. The induced voltage in the windings must be compensated to detect the voltage due to any normal transition during pulse operation. We have investigated the optimum configuration for pick-up coils (PC) for compensation. The results of simulations show that the compensated voltages are very low (70 mV) compared with the inductive voltage and adequate normal voltage sensitivity is obtained. The hot spot temperature in the CS during the operation was estimated from the simulation and the experimental data of the CSMC quench. The hot spot temperature estimated is about 144 K, lower than the ITER design criterion (150 K). It is shown that the detection system using the PCs could be designed with a high enough detection sensitivity.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:18 Percentile:75.90(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Quench characteristics of the ITER CS insert coil

Isono, Takaaki; Matsui, Kunihiro; Kato, Takashi; Takahashi, Yoshikazu; CS Model Coil Test Group; Hasegawa, Mitsuru*

Teion Kogaku, 36(6), p.373 - 380, 2001/06

no abstracts in English

JAEA Reports

Reflood experiments in single rod channel under high-pressure condition

G.Xu*; Kumamaru, Hiroshige; Tasaka, Kanji

JAERI-M 89-178, 35 Pages, 1989/11

JAERI-M-89-178.pdf:0.74MB

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:37.80(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Quench Model for Lower Temprature than Thermohydrodynamic Maximum Liquid Superheat

Murao, Yoshio

JAERI-M 10000, 27 Pages, 1982/03

JAERI-M-10000.pdf:0.75MB

no abstracts in English

JAEA Reports

A Quenching Phenomenon and Its Heat Transfer in the Subcooled Water

; ; ;

JAERI-M 8570, 42 Pages, 1979/11

JAERI-M-8570.pdf:1.14MB

no abstracts in English

JAEA Reports

Fuel Centerline Temperature Measurements in NSRR Experiments

; ; ; ;

JAERI-M 7796, 85 Pages, 1978/08

JAERI-M-7796.pdf:1.46MB

no abstracts in English

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