Evaluation method of thermal deformation for Fast Spectrum Light Water Reactor (FLWR)

Ishijima, Yasuhiro; Ioka, Ikuo; Kiuchi, Kiyoshi; Kaneko, Tetsuji*; Okubo, Tsutomu; Yamamoto, Masahiro

Atsuryoku Gijutsu, 47(1), p.12 - 17, 2009/01

http://joi.jlc.jst.go.jp/JST.Journalarchive/hpi1972/14.12

We investigate one of these innovative water reactors; Fast Spectrum Light Water Reactor (FLWR). It has unique construction for the reactor core but the fuel cladding material will be exposed in high internal pressure and axial load and complex temperature distribution. Therefore, we conducted a specially designed fatigue-creep test that were simulated several parameters (thermal distribution, temperature variation, internal pressure variation and binding stress) to evaluate an applicability of fuel cladding material for FLWR. Zircalloy-2, which is common cladding material, was used for the test. Test result was confirmed to compare the deformation value between tested and calculated. The result showed the evaluation method could be controlled several parameters simultaneously and the deformation value after the test coincided to the calculated value. This method is sufficient to evaluate thermal deformation characteristics for FLWR.

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 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 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.

Effect of tungstate inhibitor and molybdate-containing mixed phosphate-based inhibitor on corrosion of PCV steel in diluted sea water, 2

Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; Umehara, Ryuji*; Kato, Chiaki; Ueno, Fumiyoshi; et al.

no journal, , 

no abstracts in English

Effect of later added inhibitors of the steel corrosion in the diluted artificial seawater under -ray irradiation

Kato, Chiaki; Sato, Tomonori; Ueno, Fumiyoshi; Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; et al.

no journal, , 

no abstracts in English

Effect of -ray irradiation on inhibition of steel corrosion in diluted sea water

Sato, Tomonori; Kato, Chiaki; Motooka, Takafumi; Ueno, Fumiyoshi; Nakano, Junichi; Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; et al.

no journal, , 

no abstracts in English

Effect of tungstate inhibitor and molybdate-containing mixed phosphate-based inhibitor on corrosion of PCV steel in diluted sea water

Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; Umehara, Ryuji*; Kato, Chiaki; Ueno, Fumiyoshi; et al.

no journal, , 

no abstracts in English