tailieunhanh - The Gamma Ray Transmission Factor of Spent Fuel

The Gamma Ray Transmission Factor ofPassive non-destructive methodswere developed for determining total U, 235U and total Pu content of damaged spent fuel. The methods based on correlations between 137Cs and U, Pu content and using referent spent fuel assemblies. It means that the nuclear material content can be derived from measurable137Cs content, which depends on gamma ray transmission factor. In this work, this factor was determinedby aninfinite energy method and the same for both damaged and referentspent fuel with error less than 12%. Spent Fuel with error less than 12%. | VNU Journal of Science: Mathematics – Physics, Vol. 32, No. 4 (2016) 52-56 The Gamma Ray Transmission Factor of Spent Fuel Nguyen Van Quan1,*, Bui Van Loat1, Nguyen Cong Tam2 1 VNU University of Science, 334 Nguyen Trai, Hanoi, Vietnam Center of Energy Research, Hungarian Academy of Sciences 2 Received 16 November 2016 Revised 8 December 2016; Accepted 28 December 2016 Abtract: Passive non-destructive methodswere developed for determining total U, 235U and total Pu content of damaged spent fuel. The methods based on correlations between 137Cs and U, Pu content and using referent spent fuel assemblies. It means that the nuclear material content can be derived from measurable137Cs content, which depends on gamma ray transmission factor. In this work, this factor was determinedby aninfinite energy method and the same for both damaged and referentspent fuel with error less than 12%. Keywords: Passive non-destructive methods, Damaged spent fuel,Referentspent fuel,Transmission factor, Infinite energy method. 1. Introduction On the Unit 2 at Paks Nuclear Power Plant accident occurred on 2003 [1]. Due to the accident thirty fuel assemblies damaged in the cleaning tank and casing of the fuel elements and uraniumdioxide pellets in them damaged. All of them were mainly in 72 canisters containing broken fuel rods as well as pellets and parts of cladding. The canisters have two types: T28 contained materials of one or two damaged spent fuel assemblies (in separated volume) and type T29 contained an inhomogeneous mixture of spent fuel pieces of different burn-up distributed in an irregular geometry [1]. Especially, K types, is the spent fuel, which didn’t damaged and used as referent sample. Theexperimentalmethod todetermine U and Pu content need to know 137Cs and 134Cs contents (activity), whichareinversely proportional to transmission factor. The activity of 134Cs can be calculated by: A(134Cs ) CE 1 * E .BrE FE (1) where - E is the energy of .