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Journal Articles

Analysis of the direction of plasma vertical movement during major disruptions in ITER

Lukash, V.*; Sugihara, Masayoshi; Gribov, Y.*; Fujieda, Hirobumi*

Plasma Physics and Controlled Fusion, 47(12), p.2077 - 2086, 2005/12

 Times Cited Count:8 Percentile:29.48(Physics, Fluids & Plasmas)

Vertical directions of plasma movement after the thermal quench (TQ) of major disruptions in ITER are investigated using the predictive mode of the DINA code. Three dominant parameters in determining the direction of plasma movement are identified; (1) the rate of plasma current quench, (2) change of the internal plasma inductance li associated with the TQ and (3) the initial vertical position of plasma column before the TQ. It is shown that the reference ITER plasma moves upward after the TQ, if the current quench rate is higher than 200kA/ms and the drop of li does not exceed 0.2 for the present reference initial vertical position (55.5 cm above the center of machine).

Journal Articles

Edge safety factor at the onset of plasma disruption during VDEs in JT-60U

Sugihara, Masayoshi; Lukash, V.*; Khayrutdinov, R.*; Neyatani, Yuzuru

Plasma Physics and Controlled Fusion, 46(10), p.1581 - 1589, 2004/10

 Times Cited Count:11 Percentile:36.1(Physics, Fluids & Plasmas)

Detailed examinations of the value of the edge safety factor q at the onset of thermal quench during intentional VDE experiments in JT-60U are performed using two different reconstruction methods, FBI/FBEQU and DINA. Results by both methods are very similar and show that the thermal quench occurs when the q value is in the range between 1.5-2. This result suggests that the predictive simulations for VDEs should be performed within this range of q to examine the subsequent differences in the halo currents, plasma movement and other plasma behavior during the current quench.

Journal Articles

Effect of pre-hydriding on thermal shock resistance of Zircaloy-4 cladding under simulated loss-of-coolant accident conditions

Nagase, Fumihisa; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 41(7), p.723 - 730, 2004/07

 Times Cited Count:41 Percentile:92.27(Nuclear Science & Technology)

Experiments simulating loss-of-coolant accident (LOCA) conditions were performed to evaluate effect of pre-hydriding on thermal-shock resistance of oxidized Zircaloy-4 cladding. Artificially hydrided (400 to 600 ppm) and non-hydrided claddings were subjected to the tests. Since cladding fracture on quenching primarily depends on the oxidation amount, fracture threshold was evaluated in terms of "Equivalent Cladding Reacted (ECR)". Under axially non-restrained condition, the fracture threshold is 56% ECR and the influence of pre-hydriding is not seen. The fracture threshold is decreased by restraining the test rods on quenching, and it is more remarkable in pre-hydrided claddings than in non-hydrided claddings. Consequently, the fracture threshold was 20% ECR and 10% ECR for non-hydrided and pre-hydrided claddings, respectively, under the fully restrained condition. These results indicate possible decrease of fracture threshold of high burnup fuel claddings under LOCA conditions.

Journal Articles

Axisymmetric disruption dynamics including current profile changes in the ASDEX-Upgrade tokamak

Nakamura, Yukiharu; Pautasso, G.*; Gruber, O.*; Jardin, S. C.*

Plasma Physics and Controlled Fusion, 44(8), p.1471 - 1481, 2002/08

 Times Cited Count:11 Percentile:36.94(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Neutral point validation studies on JT-60U, alcator C-Mod and ASDEX-upgrade tokamaks

Nakamura, Yukiharu; Yoshino, Ryuji; Granetz, R. S.*; Pautasso, G.*; Gruber, O.*; Jardin, S. C.*

Purazuma, Kaku Yugo Gakkai-Shi, 78(4), p.347 - 355, 2002/04

no abstracts in English

Journal Articles

Present status of VDEs (Vertical Displacement Events) avoidance studies in Tokamak disruptions

Nakamura, Yukiharu

Purazuma, Kaku Yugo Gakkai-Shi, 77(9), p.843 - 856, 2001/09

no abstracts in English

Journal Articles

Burn control in tokamak fusion reactors; Disruption and fast plasma shutdown

Yoshino, Ryuji

Purazuma, Kaku Yugo Gakkai-Shi, 75(12), p.1337 - 1374, 1999/12

no abstracts in English

Journal Articles

Thermal-hydraulic model for reflooding phenomena in a PWR-LOCA

Murao, Yoshio; Iguchi, Tadashi; Sugimoto, Jun; ; Iwamura, Takamichi; Okubo, Tsutomu; Onuki, Akira

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 1, p.723 - 732, 1993/00

no abstracts in English

Journal Articles

Energy loss during disruptions and statistical analysis on disruptions

Hosogane, Nobuyuki; Yonekawa, Izuru; Itami, Kiyoshi; Nakamura, Hiroo; Kimura, Toyoaki; Nishitani, Takeo; Yoshino, Ryuji

Kaku Yugo Kenkyu, 65(SPECIAL ISSUE), p.323 - 340, 1991/03

no abstracts in English

Journal Articles

Effect of heat generation difference among fuel bundles on core thermal-hydraulics during 200% and 5% loss-of-coolant accident experiments at ROSA-III

Koizumi, Yasuo; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 24(1), p.61 - 74, 1987/01

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

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