Measurement of <sup>235</sup>U Mass and Burnup in Fuel Assembly in Research Reactors

LI Run-dong; A. V. Bushyev; A. F. Korin

Volume 30 Issue 1

Feb. 2009

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LI Run-dong, A. V. Bushyev, A. F. Korin. Measurement of 235U Mass and Burnup in Fuel Assembly in Research Reactors[J]. Nuclear Power Engineering, 2009, 30(1): 56-59.

Citation:

LI Run-dong, A. V. Bushyev, A. F. Korin. Measurement of ²³⁵U Mass and Burnup in Fuel Assembly in Research Reactors[J]. Nuclear Power Engineering, 2009, 30(1): 56-59.

LI Run-dong, A. V. Bushyev, A. F. Korin. Measurement of 235U Mass and Burnup in Fuel Assembly in Research Reactors[J]. Nuclear Power Engineering, 2009, 30(1): 56-59.

Citation:

LI Run-dong, A. V. Bushyev, A. F. Korin. Measurement of ²³⁵U Mass and Burnup in Fuel Assembly in Research Reactors[J]. Nuclear Power Engineering, 2009, 30(1): 56-59.

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Measurement of ²³⁵U Mass and Burnup in Fuel Assembly in Research Reactors

1. Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan, 621900, China;
2. Institute of Engineering and Physics, Moscow, Russia

Received Date: 2007-12-26
Rev Recd Date: 2008-07-01

Available Online: 2025-07-28

Publish Date: 2009-02-15

Abstract

Abstract

The method for measurement of ²³⁵U mass and burnup in fuel assembly in research reactors with comparison γ-Spectrum after irradiation is introduced in this paper. It also described the equipment, con-dition and experimental process of measurement IRT-3M fuel assembly in reactor IRT-MIFI in Russia, and presented relevant experiment result and its estimate of uncertainty. The result indicates the probability to ob-tain data of ²³⁵U mass in concentrated fuel assembly with uncertainty less than 2% by application of this method.
- Irradiation,
- Comparison γ-spectrum,
- Fuel assembly,
- Burnup