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Oral presentation

Reactor physics experiment using graphite-moderated core in KUCA to improve accuracy of nuclear prediction for HTGR designs

Okita, Shoichiro; Fukaya, Yuji; Goto, Masaki*; Kanda, Shun*; Nakajima, Kunihiro*; Sakon, Atsushi*; Sano, Tadafumi*; Hashimoto, Kengo*; Takahashi, Yoshiyuki*; Unesaki, Hironobu*

no journal, , 

no abstracts in English

Oral presentation

Improvement of reactivity control method for Plutonium-burner Accelerator-Driven system

Abe, Takumi*; Aizawa, Naoto*; Sugawara, Takanori; Iwasaki, Tomohiko*

no journal, , 

The accelerator-driven system for plutonium burning was designed by applying the reactivity control method for long-term operation. As a result, it was shown that the burnup reactivity loss could be reduced from 5%dk/k to 2%dk/k and the maximum cladding surface temperature could be reduced to 540$$^{circ}$$C for a 200-day operation period by optimizing the burnable poison assembly loaded in the core.

Oral presentation

Analysis of criticality incident at Windscale Works

Fukuda, Kodai; Yamane, Yuichi

no journal, , 

A preliminary analysis of the criticality incident at Windscale Works in 1970 was performed. The open-source CFD tool box OpenFOAM and the Monte Carlo neutron transport calculation code MVP3.0 were used for the analysis. As the result, the progress of the incident and the change of reactivity during the incident were confirmed.

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