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Journal Articles

Thresholds for failure of high-burnup LWR fuels by pellet cladding mechanical interaction under reactivity-initiated accident conditions

Udagawa, Yutaka; Sugiyama, Tomoyuki; Amaya, Masaki

Journal of Nuclear Science and Technology, 56(12), p.1063 - 1072, 2019/12

 Times Cited Count:12 Percentile:68.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis on split failure of cladding of high burnup BWR rods in reactivity-initiated accident conditions by RANNS code

Suzuki, Motoe; Saito, Hiroaki*; Fuketa, Toyoshi

Nuclear Engineering and Design, 236(2), p.128 - 139, 2006/01

 Times Cited Count:8 Percentile:47.76(Nuclear Science & Technology)

A computer code RANNS was developed to analyze fuel rod behaviors in the RIA conditions. The code performs thermal and FEM-mechanical calculation for a single rod in axis-symmetric geometry to predict temperature profile, PCMI contact pressure, stress-strain distribution and their interactions. An experimental analysis by RANNS begins with pre-test conditions of irradiated rod which are given by FEMAXI-6. Analysis was performed on the simulated RIA experiments in NSRR, FK-10 and FK-12, of high burnup BWR rods in a cold start-up conditions, and PCMI process was discussed extensively. It was revealed that pellet thermal expansion dominates cladding deformation and subjects the cladding to bi-axial stress state, and thermal expansion in the cladding makes the stress in the inner region significantly lower than that in the outer region. Simulation calculations with wider pulses were carried out and the resulted cladding hoop stress was compared with the failure stress estimated in the NSRR experiments.

Journal Articles

RANNS code analysis on the local mechanical conditions of cladding of high burnup fuel rods under PCMI in RIA-simulated experiments in NSRR

Suzuki, Motoe; Saito, Hiroaki*; Fuketa, Toyoshi

Proceedings of 2005 Water Reactor Fuel Performance Meeting (CD-ROM), p.579 - 601, 2005/10

The RANNS code analyzes behaviors of a single fuel rod in reactivity-initiated accident (RIA) conditions. The code has two types of mechanical model; one-dimensional deformation model for each axial segment length of rod, and newly-developed two-dimensional local deformation model for one pellet length. Analyses were performed on the two RIA-simulated experiments in the NSRR, OI-10 and OI-11 with high burnup PWR rods, and results of cladding deformation were compared between calculations by the two models and PIE data. RANNS calculated the deformation profiles of claddings during the power transient of the experiments on the basis of the pre-pulse conditions of rods predicted by FEMAXI-6 code. In the calculations by the two-dimensional model, the plastic strain increase at the cladding ridges was compared with those in between the ridges and with the PIE data, and effect of stress variance induced by local non-uniformity of strain on the crack growth was discussed.

JAEA Reports

High burnup (41$$sim$$61GWd/tU) BWR fuel behavior under reactivity initiated accident conditions

Nakamura, Takehiko; Kusagaya, Kazuyuki*; Yoshinaga, Makio; Uetsuka, Hiroshi

JAERI-Research 2001-054, 49 Pages, 2001/12

JAERI-Research-2001-054.pdf:6.7MB

no abstracts in English

Journal Articles

Phenomenon identification and ranking tables (PIRTs) for rod ejection accidents in pressurized water reactors containing high burnup fuel

Boyack, B. E.*; Motta, A. T.*; Peddicord, K. L.*; Alexander, C. A.*; Deveney, R. C.*; Dunn, B. M.*; Fuketa, Toyoshi; Higar, K. E.*; Hochreiter, L. E.*; Langenbuch, S.*; et al.

NUREG/CR-6742, 263 Pages, 2001/09

no abstracts in English

Journal Articles

Mechanical energy generation during high burnup fuel failure under reactivity initiated accident conditions

Sugiyama, Tomoyuki; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 37(10), p.877 - 886, 2000/10

no abstracts in English

Journal Articles

Behavior of PWR and BWR fuels during reactivity-initiated accident conditions

Fuketa, Toyoshi; Nakamura, Takehiko; Sasajima, Hideo; Nagase, Fumihisa; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of an International Topical Meeting on Light Water Reactor Fuel Performance (CD-ROM), 15 Pages, 2000/00

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

Journal Articles

Mechanical energy generation during high burnup fuel failure under reactivity initiated accident conditions

; Fuketa, Toyoshi; Ishijima, Kiyomi

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

New results from the NSRR experiments with high burnup fuel

Fuketa, Toyoshi; Ishijima, Kiyomi; ; Sasajima, Hideo;

NUREG/CP-0149 (Vol. 1), 0, p.45 - 63, 1996/00

no abstracts in English

JAEA Reports

Behavior of pre-irradiated fuel under a simulated RIA condition; Results of NSRR test JM-5

Fuketa, Toyoshi; Sasajima, Hideo; ; ; Tanzawa, Sadamitsu; Ishijima, Kiyomi; ; ;

JAERI-Research 95-078, 194 Pages, 1995/11

JAERI-Research-95-078.pdf:17.91MB

no abstracts in English

JAEA Reports

Behavior of pre-irradiated fuel under a simulated RIA condition; Results of NSRR test JM-4

Fuketa, Toyoshi; ; Sasajima, Hideo; ; Tanzawa, Sadamitsu; Ishijima, Kiyomi; ; Kikuchi, Teruo;

JAERI-Research 95-013, 230 Pages, 1995/03

JAERI-Research-95-013.pdf:24.22MB

no abstracts in English

14 (Records 1-14 displayed on this page)
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