JOPSS - Search Results

Journal Articles

Removal of the inpile-tube of the high temperature high pressure water loop OWL-2 from the reactor pressure vessel

; Amagai, Tomio; Watanabe, Hiroyuki;

UTNL-R-0292, p.1 - 9, 1993/00

no abstracts in English

JAEA Reports

Prediction of thermal behavior of FBR fuel in the NSRR transient tests

Nakamura, Takehiko; Sobajima, Makoto; *

JAERI-M 90-140, 189 Pages, 1990/09

JAERI-M-90-140.pdf:3.97MB

no abstracts in English

Journal Articles

Conceptual design of research and development facility for fusion reactor blanket

Mori, Seiji*; *; Seki, Yasushi; Seki, Masahiro

FAPIG, 0(124), p.2 - 11, 1990/03

no abstracts in English

JAEA Reports

A Study on Gap Heat Transfer of LWR Fuel Rods under Reactivety Initiated Accident Conditions

JAERI-M 84-063, 166 Pages, 1984/03

JAERI-M-84-063.pdf:5.94MB

no abstracts in English

JAEA Reports

Fuel Centerline Temperature Measurement Experiment in JMTR,VI; Design and Fabrication of the Second Assembly

; ; ; ;

JAERI-M 82-187, 51 Pages, 1982/12

JAERI-M-82-187.pdf:1.63MB

no abstracts in English

JAEA Reports

The Effects of Coolant Flow on Fuel Behavior Under RIA Conditions(2); NSRR Inpile Loop Test Results

; ; ;

JAERI-M 82-137, 51 Pages, 1982/10

JAERI-M-82-137.pdf:1.6MB

no abstracts in English

JAEA Reports

Fuel Centerline Temperature Measurement Experiment in JMTR[I] - Design and Fabrication of the First Test Assembly(77LF-33J) -

; ; ;

JAERI-M 9600, 68 Pages, 1981/08

JAERI-M-9600.pdf:2.66MB

no abstracts in English

JAEA Reports

Calibration of Energy Deposition into the NSRR Test Fuel Rod by Colorimetric Measurement

; ;

JAERI-M 8457, 36 Pages, 1979/10

JAERI-M-8457.pdf:1.01MB

no abstracts in English

JAEA Reports

Surveillance Test of OWL-2 Inpile Tube

;

JAERI-M 6667, 33 Pages, 1976/08

JAERI-M-6667.pdf:0.83MB

no abstracts in English

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Removal of the inpile-tube of the high temperature high pressure water loop OWL-2 from the reactor pressure vessel

Prediction of thermal behavior of FBR fuel in the NSRR transient tests

Conceptual design of research and development facility for fusion reactor blanket

A Study on Gap Heat Transfer of LWR Fuel Rods under Reactivety Initiated Accident Conditions

Fuel Centerline Temperature Measurement Experiment in JMTR,VI; Design and Fabrication of the Second Assembly

The Effects of Coolant Flow on Fuel Behavior Under RIA Conditions(2); NSRR Inpile Loop Test Results

Fuel Centerline Temperature Measurement Experiment in JMTR[I] - Design and Fabrication of the First Test Assembly(77LF-33J) -

Calibration of Energy Deposition into the NSRR Test Fuel Rod by Colorimetric Measurement

Surveillance Test of OWL-2 Inpile Tube