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JAEA Reports

Development of testing techniques to evaluate thermal deformation behavior of fuel cladding tubes (Contract research)

Kaneko, Tetsuji; Tsukatani, Ichiro; Kiuchi, Kiyoshi

JAERI-Tech 2004-035, 18 Pages, 2004/03

JAERI-Tech-2004-035.pdf:0.81MB

Fuel elements used in the Reduced-Moderation Water Reactor (RMWR) have the stacking structure consisting of MOX pellets and UO$$_{2}$$ blankets in a fuel rod in order to attain the high breeding ratio and high burn-up simultaneously. It is a characteristic of the fuel elements that there is high thermal stress caused by inhomogeneous linear power density along the longitudinal direction of the fuel rod in comparison with the present LWR fuels. For this reason, it is important to estimate local deformation behavior of the fuel cladding tube with temperature difference caused by MOX pellet and UO$$_{2}$$ blanket. The testing machine was designed to investigate thermal-fatigue behavior under biaxial stress condition. The testing machine consists of the temperature distribution control unit, low cycle fatigue testing unit and internal pressure loading unit, it is also possible to conduct the simulation tests to investigate effects of pressure change with burn-up and longitudinal load change due to operation modes and restriction of fuel rods.

Journal Articles

Dismantling techniques for reactor steel structures

Yanagihara, Satoshi; ; Nakamura, Hisashi

Nuclear Technology, 86, p.148 - 158, 1989/08

 Times Cited Count:11 Percentile:75.69(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Efect of Fuel Peller Densifieation on Fuel Rod Internal Pressure

; ; ; *

JAERI-M 6631, 18 Pages, 1976/07

JAERI-M-6631.pdf:0.62MB

no abstracts in English

JAEA Reports

Consideration of Average Temperature in Fuel Rod Plasma

; ; ;

JAERI-M 6249, 10 Pages, 1975/09

JAERI-M-6249.pdf:0.44MB

no abstracts in English

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