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Journal Articles

Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 $$times$$ 17 type PWR fuel cladding tube under LOCA-simulated burst conditions

Furumoto, Kenichiro; Udagawa, Yutaka

Journal of Nuclear Science and Technology, 60(5), p.500 - 511, 2023/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

JAEA Reports

Cladding tube burst experiment assumed MA fuel pin for transmutation physics experimental facility

Sugawara, Takanori; Tsujimoto, Kazufumi

JAEA-Research 2017-011, 35 Pages, 2017/10

JAEA-Research-2017-011.pdf:4.88MB

The construction of Transmutation Physics Experimental Facility (TEF-P) is planned in the J-PARC project. TEF-P is a critical assembly and it will treat minor actinide (MA) fuel in the experiment. The temperature when the air cooling for the TEF-P core would stop was estimated but there were no data to evaluate the soundness of the MA fuel pin. To set a tentative limit temperature for the TEF-P core, cladding tube burst experiment was performed. As the result, the cladding tube burst occurred at 660$$^{circ}$$C as the severest case. Through these results and the estimation of creep rupture time, the tentative limit temperature for the TEF-P core was set to 600$$^{circ}$$C.

Journal Articles

Investigation of hydride rim effect on failure of Zircaloy-4 cladding with tube burst test

Nagase, Fumihisa; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 42(1), p.58 - 65, 2005/01

 Times Cited Count:47 Percentile:92.75(Nuclear Science & Technology)

Tube burst tests have been performed with artificially hydrided Zircaloy-4 specimens at room temperature and at 620 K. Pressurization rate was increased to a maximum of 3.4 GPa/s in order to simulate rapid PCMI that occurs in high burnup fuel rods during a pulse-irradiation in the NSRR. Hydrogen content in the specimens ranged from 150 to 1050 ppm. Hydrides were accumulated in the cladding periphery and formed "hydride rim" as observed in high burnup PWR fuel claddings. The hydrided cladding tubes failed with an axial crack at the room temperature tests. Brittle fracture appeared in the hydride rim, and failure morphology was similar to that observed in the NSRR experiments. The hydrides rim obviously reduced burst pressure and residual hoop strain at the tests. The residual hoop strain was very small even at 620 K when thickness of the hydride rim exceeded 18% of cladding thickness. The present result accordingly indicates an important role of the hydrides layer in high burnup fuel rod failure under RIA conditions.

Journal Articles

Influence of hydride re-orientation on BWR cladding rupture under accidental conditions

Nagase, Fumihisa; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 41(12), p.1211 - 1217, 2004/12

 Times Cited Count:19 Percentile:75.21(Nuclear Science & Technology)

Hydride precipitation along the radial-axial plane increases in high burn-up BWR fuel claddings. The radial hydrides may have an important role during fuel behavior in a RIA and may reduce ductility of the cladding under PCMI conditions. In order to promote a better understanding of the influence of the radial hydrides on cladding failure behavior under the PCMI conditions, tube burst tests were conducted for unirradiated BWR claddings charged with 200 to 650 ppm of hydrogen. About 20 to 30% of hydrides were re-oriented and precipitated along the radial-axial plane. The claddings exhibited large burst openings with an axial crack at room temperature and 373 K. However, the influence of the radial hydrides on both burst pressure and residual hoop strain was very small. It is accordingly expected that ductility of high burn-up BWR cladding is significantly reduced not only by precipitation of radial hydrides as far as hydrogen concentration and radial hydride fraction range in the present study.

JAEA Reports

Investigation of evaluation model of mist release behavior from burst of bubble on the solution surface

Abe, Hitoshi; Tashiro, Shinsuke; Morita, Yasuji

JAERI-Research 2004-014, 19 Pages, 2004/09

JAERI-Research-2004-014.pdf:1.33MB

no abstracts in English

Journal Articles

Recent progress of SOL and divertor plasma studies in Tokamaks

Asakura, Nobuyuki

Purazuma, Kaku Yugo Gakkai-Shi, 80(3), p.190 - 200, 2004/03

Understanding of the divertor and Scrape-off Layer (SOL) plasmas has been progressed during improvements of the compact- and closed-geometry tokamak divertors. Developments of new diagnostics viewing the SOL and upstream of the divertor target (with the finest spatial and/or time resolutions) have contributed to understand the physics mechanisms under large variations of the plasma along and perpendicular to the field lines. Four topics: (i) heat and particle transports upstream of the divertor plate, (ii) burst transport of heat and particles towards the divertor, (iii) SOL plasma flow, and (iv) plasma diffusion in SOL, were reviewed.

Journal Articles

A Time pickup system for monitoring cyclotron beam bursts

Okumura, Susumu; Fukuda, Mitsuhiro; Ishibori, Ikuo; Arakawa, Kazuo

Review of Scientific Instruments, 73(1), p.51 - 55, 2002/01

 Times Cited Count:1 Percentile:12.5(Instruments & Instrumentation)

We have developed a time pickup system for monitoring the beam bursts from a cyclotron. The time pickup can measure the phase and the width of the beam bursts by detecting secondary electrons emitted from a foil or a wire target inserted into the beam with time resolutions around 200 ps FWHM (full width at half maximum) in spite of its simple structure. Using the foil and the wire targets appropriately, monitoring the bursts of variety of beams can be achieved. In addition, by adjusting the position of the target, enough detection rate of the beam burst is obtained with minimized interference with the beam. The present investigation shows that it is needed to adjust the collection voltage of the time pickup according to the purposes: the optimum collection voltages for high resolution measurement are in the range from -0.5 to -1.0 kV and those for high efficiency measurement are not less than -4.0 kV.

Journal Articles

Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel

Boyack, B. E.*; Motta, A. T.*; Peddicord, K. L.*; Alexander, C. A.*; Andersen, J. G. M.*; Blaisdell, J. A.*; Dunn, B. M.*; Ebeling-Koning, D.*; Fuketa, Toyoshi; Hache, G.*; et al.

NUREG/CR-6744, 455 Pages, 2001/12

no abstracts in English

Journal Articles

Phenomenon identification and ranking tables (PIRTs) for power oscillations without scram in boiling water reactors containing high burnup fuel

Boyack, B. E.*; Motta, A. T.*; Peddicord, K. L.*; Andersen, J. G. M.*; Alexander, C. A.*; Dunn, B. M.*; Fuketa, Toyoshi; Hochreiter, L. E.*; Montgomery, R. O.*; Moody, F. J.*; et al.

NUREG/CR-6743, 266 Pages, 2001/09

no abstracts in English

JAEA Reports

High-pressurization-rate burst test of hydrided zircaloy-4 fuel cladding at 620K

Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi

JAERI-Research 2000-046, 31 Pages, 2000/12

JAERI-Research-2000-046.pdf:3.72MB

no abstracts in English

JAEA Reports

Design and fabrication of cladding tube burst test apparatus with high pressurization rates

Otomo, Takashi; Nagase, Fumihisa; Uetsuka, Hiroshi

JAERI-Tech 99-071, p.25 - 0, 1999/10

JAERI-Tech-99-071.pdf:1.84MB

no abstracts in English

JAEA Reports

High-pressurization-rate burst test of hydrided Zircaloy-4 fuel cladding at room temperature

Nagase, Fumihisa; ; Uetsuka, Hiroshi

JAERI-Research 98-064, 25 Pages, 1998/11

JAERI-Research-98-064.pdf:2.17MB

no abstracts in English

JAEA Reports

Proposal of safety design methodologies for an HTGR-hydrogen production system; Mainly on countermeasures against fire and explosion

Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku

JAERI-Research 97-022, 110 Pages, 1997/03

JAERI-Research-97-022.pdf:4.1MB

no abstracts in English

Journal Articles

Effects of waterlogged fuel rod rupture on adjacent fuel rods and channel box under an RIA conditions

;

Journal of Nuclear Science and Technology, 24(1), p.23 - 32, 1986/01

 Times Cited Count:1 Percentile:19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study of accident scenario ofChernobyl power reactor

; *; ; *;

Genshiryoku Kogyo, 32(12), p.17 - 31, 1986/00

no abstracts in English

Journal Articles

Effect of burst temperature on coolant channel restriction in multirods burst tests

; ; ; ;

Journal of Nuclear Science and Technology, 20(3), p.246 - 253, 1983/00

 Times Cited Count:3 Percentile:44.38(Nuclear Science & Technology)

no abstracts in English

32 (Records 1-20 displayed on this page)