Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 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

OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Influence of pellet geometry and gap size

Soba, A.*; Prudil, A.*; Zhang, J.*; Dethioux, A.*; Han, Z.*; Dostal, M.*; Matocha, V.*; Marelle, V.*; Lasnel-Payan, J.*; Kulacsy, K.*; et al.

Proceedings of TopFuel 2021 (Internet), 10 Pages, 2021/10

Journal Articles

Fission gas release in irradiated UO$$_{2}$$ fuel at burnup of 45 GWd/t during simulated Reactivity Initiated Accident (RIA) condition

Amaya, Masaki; Sugiyama, Tomoyuki; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 41(10), p.966 - 972, 2004/10

 Times Cited Count:9 Percentile:50.87(Nuclear Science & Technology)

Pulse irradiation simulating RIA condition was carried out for test rod prepared from fuel irradiated in a commercial reactor. After the pulse irradiation, optical microscopy (OM) and scanning electron microscopy (SEM) observations and electron probe micro analysis (EPMA) were conducted for the test rod as a part of destructive tests. Fission gas release behavior during pulse irradiation was investigated by EPMA and puncture test. Xeon depression was observed in the fuel pellet after pulse irradiation at periphery and center region. It is considered that fission gas was mainly released from the pellet center region during pulse irradiation. The amount of xenon release during pulse irradiation was estimated to be 10-12% from the EPMA results and this estimated value was comparable with the puncture test result. Comparing the estimated value with other results of out-of-pile annealing tests, it was concluded that most fission gas, which was accumulated at grain boundary during base irradiation, was released from the center region of test fuel pellet during pulse irradiation.

Journal Articles

Rim structure formation of isothermally irradiated UO$$_{2}$$ fuel discs

Une, Katsumi*; Nogita, Kazuhiro*; Shiratori, Tetsuo; Hayashi, Kimio

Journal of Nuclear Materials, 288(1), p.20 - 28, 2000/09

 Times Cited Count:22 Percentile:80.09(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Out-pile FP Release Experiment by Heating of Irradiated UO$$_{2}$$ Pellet

;

JAERI-M 85-199, 16 Pages, 1985/12

JAERI-M-85-199.pdf:0.68MB

no abstracts in English

JAEA Reports

Semiannual Progress Report on the NSRR Experiments,8

JAERI-M 8779, 75 Pages, 1980/03

JAERI-M-8779.pdf:2.86MB

no abstracts in English

5 (Records 1-5 displayed on this page)
  • 1