Refine your search:     
Report No.
 - 
Search Results: Records 1-8 displayed on this page of 8
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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:93.51(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.

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

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:19.33(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

Effects of rod pre-pressurization on light water reactor fuel behavior during reactivity accident conditions

; ; ;

Journal of Nuclear Science and Technology, 19(4), p.289 - 306, 1982/00

 Times Cited Count:10 Percentile:71.34(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Study of fuel behavior under reactivity initiated accident conditions; Review

;

Journal of Nuclear Materials, 95(1-2), p.1 - 30, 1980/00

 Times Cited Count:33 Percentile:92.51(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Semiannual Progress Report on the NSRR Experiments(7)

;

JAERI-M 8259, 91 Pages, 1979/05

JAERI-M-8259.pdf:3.44MB

no abstracts in English

8 (Records 1-8 displayed on this page)
  • 1