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Search Results: Records 1-16 displayed on this page of 16
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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

Journal Articles

The current status of nuclear codes development in Japan

; ; Katsuragi, Satoru; *; ; *; *; *; Sanokawa, Konomo; ; et al.

Nihon Genshiryoku Gakkai-Shi, 17(7), p.329 - 348, 1975/07

https://doi.org/10.3327/jaesj.17.329

no abstracts in English

JAEA Reports

Design and Safety Features of Commercial Nuclear Power Plant in USA; Nuclear

;

JAERI-M 5995, 35 Pages, 1975/02

JAERI-M-5995.pdf:1.26MB

no abstracts in English

JAEA Reports

Design Data and Safety Features of Commercial Nuclear Power Plant in USA; Thermal Hydrauric

;

JAERI-M 5987, 38 Pages, 1975/02

JAERI-M-5987.pdf:1.52MB

no abstracts in English

JAEA Reports

Design Data and Safety Features of Commercial Nuclear Power Plant in USA,General Descriptions

;

JAERI-M 5968, 27 Pages, 1975/01

JAERI-M-5968.pdf:0.94MB

no abstracts in English

JAEA Reports

Design Data and Safety Features of Commercial Nuclear Power Plants, Japan

; ;

JAERI-M 5959, 118 Pages, 1975/01

JAERI-M-5959.pdf:3.71MB

no abstracts in English

JAEA Reports

FREG-1; A Computer Program for Calculating the Gap Conductance in Oxide Fuel Pins

; ; ; ; ; ; *

JAERI-M 5958, 51 Pages, 1975/01

JAERI-M-5958.pdf:1.45MB

no abstracts in English

JAEA Reports

Description of Computer Program for Fuel Performance

; ; ; ; ;

JAERI-M 5628, 90 Pages, 1974/03

JAERI-M-5628.pdf:2.55MB

no abstracts in English

Journal Articles

Jntroduction to Reactor Safety

; ;

Genshiryoku Kogyo, 19(11), p.59 - 62, 1973/11

http://ci.nii.ac.jp/naid/40017723065

no abstracts in English

JAEA Reports

The Diagram of Zircaloy-2 Corrosion for the Reactor Fuel Design

; ; ;

JAERI-M 5423, 10 Pages, 1973/10

JAERI-M-5423.pdf:0.73MB

no abstracts in English

JAEA Reports

JPDR-II Poison Curtain Design and Fabrication Report

; ; ; ;

JAERI-M 5015, 60 Pages, 1972/10

JAERI-M-5015.pdf:1.66MB

no abstracts in English

JAEA Reports

The Desigh for Power Reactor Fuel Assembly Vol 1,Desigh Data of Temperature Heart Flux Distribution and Mechanical Strength

; ; ; ; ;

JAERI-M 4881, 297 Pages, 1972/07

JAERI-M-4881.pdf:21.09MB

no abstracts in English

Journal Articles

Uranium Dioxide Fuel Pin Elongation Behavior under Irradiation

; ; ;

Journal of Nuclear Science and Technology, 8(9), p.528 - 530, 1971/09

https://doi.org/10.3327/jnst.8.528

no abstracts in English

JAEA Reports

Helium purification system of High Temperature Gas-cooled Reactor

; ; *; Naito, Keiji; *; *; *

JAERI 1051, 51 Pages, 1964/01

JAERI-1051.pdf:2.66MB

no abstracts in English

Journal Articles

The trend of various nuclear reactors for power,C; Liquid metal reactor

Nihon Kikai Gakkai-Shi, 65(520), p.662 - 665, 1962/00

http://ci.nii.ac.jp/naid/110002460970

no abstracts in English

JAEA Reports

Description and Hazard Analysis of Semi-Homogeneous Experiment

; ; ; *;

JAERI 4014, 26 Pages, 1960/08

JAERI-4014.pdf:2.73MB

no abstracts in English

16 (Records 1-16 displayed on this page)
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