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Search Results: Records 1-14 displayed on this page of 14
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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

Fracture-mechanics-based evaluation of failure limit on pre-cracked and hydrided Zircaloy-4 cladding tube under biaxial stress states

Li, F.; Mihara, Takeshi; Udagawa, Yutaka; Amaya, Masaki

Journal of Nuclear Science and Technology, 57(6), p.633 - 645, 2020/06

https://doi.org/10.1080/00223131.2019.1709996
 Times Cited Count：3 Percentile：24.28(Nuclear Science & Technology)

Journal Articles

Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS

Taniguchi, Yoshinori; Udagawa, Yutaka; Amaya, Masaki

Annals of Nuclear Energy, 139, p.107188_1 - 107188_7, 2020/05

https://doi.org/10.1016/j.anucene.2019.107188
 Times Cited Count：1 Percentile：12.16(Nuclear Science & Technology)

Journal Articles

The Effect of base irradiation on failure behaviors of UO$$_{2}$$ and chromia-alumina additive fuels under simulated reactivity-initiated accidents; A Comparative analysis with FEMAXI-8

Udagawa, Yutaka; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Amaya, Masaki

Annals of Nuclear Energy, 139, p.107268_1 - 107268_9, 2020/05

AA2019-0372.pdf:0.81MB

https://doi.org/10.1016/j.anucene.2019.107268
 Times Cited Count：3 Percentile：35.51(Nuclear Science & Technology)

Journal Articles

OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Impact of number of radial pellet cracks and pellet-clad friction coefficient

Dost$'a$l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; Amaya, Masaki; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10

Journal Articles

Transient elongation of a fresh fuel rod under reactivity initiated accident conditions

Ishijima, Kiyomi; Nakamura, Takehiko

Journal of Nuclear Science and Technology, 33(3), p.229 - 238, 1996/03

https://doi.org/10.3327/jnst.33.229
 Times Cited Count：7 Percentile：54.42(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Pellet-cladding mechanical interaction of PWR fuel rod under rapid power transient

Yanagisawa, Kazuaki; Katanishi, Shoji;

Journal of Nuclear Science and Technology, 31(7), p.671 - 676, 1994/07

https://doi.org/10.3327/jnst.31.671
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

In-pile eddy current test on PWR fuel rod failed by pellet-cladding interaction

; T.Johnsen*

Journal of Nuclear Science and Technology, 23(8), p.752 - 755, 1986/00

https://doi.org/10.3327/jnst.23.752
 Times Cited Count：1 Percentile：28.17(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study of pellet-cladding interaction on light water reactor fuel, (I); PWR type fuel rod

; *; E.Kolstad*

Nihon Genshiryoku Gakkai-Shi, 28(7), p.641 - 657, 1986/00

https://doi.org/10.3327/jaesj.28.641
 Times Cited Count：4 Percentile：48.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A study on bamboo ridge deformation induced by pellet cladding interaction

; *

Nucl.Eng.Des., 97, p.339 - 346, 1986/00

https://doi.org/10.1016/0029-5493(86)90169-X
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

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

JAEA Reports

Irradiation,Past Irradiation Examination and Evaluation of IFA-208 and 224

JAERI-M 7726, 95 Pages, 1978/07

JAERI-M-7726.pdf:6.84MB

no abstracts in English

JAEA Reports

Plans for Irradiation Experiments of IFA's 508 and 515,and Preliminary Data Report for IFA's 508

JAERI-M 7530, 70 Pages, 1978/02

JAERI-M-7530.pdf:1.76MB

no abstracts in English

Oral presentation

Comparative analysis on base-irradiation behaviors of OS-1 test rod and other BWR-fuel rods subjected to previous NSRR tests

Udagawa, Yutaka

no journal, , 

14 (Records 1-14 displayed on this page)
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