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Journal Articles

Estimation for temperature distribution in a heat-generating cylinder with multiple holes

; Hoshiya, Taiji; ; Niimi, Motoji; *

Journal of Nuclear Science and Technology, 30(4), p.291 - 301, 1993/04

https://doi.org/10.3327/jnst.30.291
 Times Cited Count：4 Percentile：44.86(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

SATCAP-C: A Program for thermal hydraulic design of pressurized water injection type capsule

; ; Aso, Tomokazu; Niimi, Motoji

JAERI-M 92-149, 78 Pages, 1992/10

JAERI-M-92-149.pdf:2.53MB

no abstracts in English

Journal Articles

Effect of eccentric pellet on gap conductance in fuel rod

; ; Hoshiya, Taiji

Journal of Nuclear Science and Technology, 28(10), p.961 - 964, 1991/10

https://doi.org/10.3327/jnst.28.961

no abstracts in English

JAEA Reports

Thermal analysis of boiling water capsule

; *; ; Nakamura, Jinichi; Uchida, Masaaki

JAERI-M 91-003, 38 Pages, 1991/02

JAERI-M-91-003.pdf:1.22MB

no abstracts in English

JAEA Reports

Design procedure of capsule with multistage heater control, named MUSTAC

; Endo, Yasuichi; Hoshiya, Taiji; Niimi, Motoji;

JAERI-M 90-214, 57 Pages, 1990/11

JAERI-M-90-214.pdf:1.59MB

no abstracts in English

JAEA Reports

Analysis of effect of variation of gap size in buckled cladding on temperature and heat flux distribution of fuel rod

Hoshiya, Taiji; ; *;

JAERI-M 89-199, 35 Pages, 1989/12

JAERI-M-89-199.pdf:1.0MB

no abstracts in English

JAEA Reports

SATCAP-B; A Program for thermal-hydraulic design of saturated temperature capsule

; ; Niimi, Motoji

JAERI-M 89-187, 60 Pages, 1989/11

JAERI-M-89-187.pdf:1.63MB

no abstracts in English

JAEA Reports

Thermal characteristic test for saturated temperature type capsule

Niimi, Motoji; ; *; ;

JAERI-M 89-099, 30 Pages, 1989/08

JAERI-M-89-099.pdf:0.78MB

no abstracts in English

JAEA Reports

CAPSTAR: A program to evaluate safety strength for outer/inner tubes of capsules

*; Hoshiya, Taiji; Niimi, Motoji; ;

JAERI-M 88-121, 36 Pages, 1988/07

JAERI-M-88-121.pdf:0.78MB

no abstracts in English

JAEA Reports

SATCAP; A program for thermal-hydraulic design of saturated temperature capsule

; *; Niimi, Motoji;

JAERI-M 88-013, 49 Pages, 1988/02

JAERI-M-88-013.pdf:1.3MB

no abstracts in English

JAEA Reports

GENGTC-JB: A computer program to calculate temperature distribution for cylindrical geometry capsule

; *; Niimi, Motoji; Hoshiya, Taiji;

JAERI-M 87-148, 25 Pages, 1987/09

JAERI-M-87-148.pdf:0.69MB

no abstracts in English

JAEA Reports

Reactor Fuel Performance Date File -1985 edition-

; ; *

JAERI-M 86-101, 205 Pages, 1986/07

JAERI-M-86-101.pdf:4.33MB

no abstracts in English

Journal Articles

Oxidation of 304 stainless steel in high-temperature steam

; ; Yaguchi, Shinnosuke*

Journal of Nuclear Materials, 140, p.74 - 84, 1986/00

https://doi.org/10.1016/0022-3115(86)90198-4
 Times Cited Count：21 Percentile：86.83(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Analysis of effect of eccentric holes in pellets on temperature and heat flux distribution in a fuel rod

; *

Journal of Nuclear Science and Technology, 23(2), p.151 - 159, 1986/00

https://doi.org/10.3327/jnst.23.151
 Times Cited Count：5 Percentile：54.53(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

FREC-4A : A Computer Program to Predict Fuel Rod Performance under Normal Reactor Operation

;

JAERI-M 9683, 140 Pages, 1981/10

JAERI-M-9683.pdf:3.19MB

no abstracts in English

JAEA Reports

FREG-4: A Computer Program to Predict the Fuel-to-Cladding Heat Transfer Coefficient in Accordance with Fuel-Rod Irradiation History

; ; *

JAERI-M 9631, 71 Pages, 1981/08

JAERI-M-9631.pdf:1.8MB

no abstracts in English

JAEA Reports

Data List of Nuclear Power Plants of Pressurized-Water Reactor Type in Japan

;

JAERI-M 9629, 274 Pages, 1981/08

JAERI-M-9629.pdf:7.06MB

no abstracts in English

JAEA Reports

Design Data and Safety Features of Commercial Nuclear Plants in Japan; 1979 edition

; ; ;

JAERI-M 8947, 420 Pages, 1980/07

JAERI-M-8947.pdf:12.38MB

no abstracts in English

JAEA Reports

FREG-3T: A Computer Program To Analyse LWR Fuel Behavior Under Accident Conditions

; ; *

JAERI-M 8482, 56 Pages, 1979/10

JAERI-M-8482.pdf:1.5MB

no abstracts in English

JAEA Reports

Finite Element Method Programs to Analyse Irradiation Performance of a Fuel Pellet

; ; *; *

JAERI-M 8468, 77 Pages, 1979/09

JAERI-M-8468.pdf:1.55MB

no abstracts in English

47 (Records 1-20 displayed on this page)