SEDL / STP / STP1228-EB / STP15143S

The Irradiation Facility Korpus for Irradiation of the Reactor Structure Materials

Brodkin, EB
Senior scientist, senior scientist and head of department, Russian Research Centre “Kurchatov Institute”, Moscow,

Egorov, AL
Senior scientist, senior scientist and head of department, Russian Research Centre “Kurchatov Institute”, Moscow,

Golovanov, VN
Head of department, head of laboratory, senior scientist, head of department and deputy director, Research Institute of Atomic Reactors (RIAR), Dimitrovgrad, Ulianovsk region

Markina, NV
Head of department, head of laboratory, senior scientist, head of department and deputy director, Research Institute of Atomic Reactors (RIAR), Dimitrovgrad, Ulianovsk region

Raetsky, VM
Head of department, head of laboratory, senior scientist, head of department and deputy director, Research Institute of Atomic Reactors (RIAR), Dimitrovgrad, Ulianovsk region

Sulaberidze, VS
Head of department, head of laboratory, senior scientist, head of department and deputy director, Research Institute of Atomic Reactors (RIAR), Dimitrovgrad, Ulianovsk region

Tsikanov, VA
Head of department, head of laboratory, senior scientist, head of department and deputy director, Research Institute of Atomic Reactors (RIAR), Dimitrovgrad, Ulianovsk region

Zaritsky, SM
Senior scientist, senior scientist and head of department, Russian Research Centre “Kurchatov Institute”, Moscow,

Pages: 10    Published: Jan 1994

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Abstract

The results concerning the irradiation embrittlement of WWER vessel materials prove the necessity of organizing experiments in controllable and adjustable conditions ensuring the unequivocal interpretation of the change of material properties under irradiation. The KORPUS facility for RBT-6 reactor was designed and made for the realization of controllable irradiation with the possibility of a simulation of reactor WWER vessel materials working conditions. The KORPUS design and technical characteristics are considered in this paper. Its experimental possibilities from the point of view of material testing and reactor dosimetry execution are discussed. The precomputation results indicative of possible simulation of vessel material working conditions are presented. The proposals on creating dosimetry experimental conditions are formulated.