A Concise Design for Irradiating U-10Zr Metallic Fuel at Very Low Burnup

Haibing Guo; Wei Zhou; Yong Sun; Dazhi Qian; Jimin Ma; Jun Leng; Heyong Huo; Shaohua Wang

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자료유형: 학술저널

저자정보: Haibing Guo (China Academy of Engineering Physics) Wei Zhou (China Academy of Engineering Physics) Yong Sun (China Academy of Engineering Physics) Dazhi Qian (China Academy of Engineering Physics) Jimin Ma (China Academy of Engineering Physics) Jun Leng (China Academy of Engineering Physics) Heyong Huo (China Academy of Engineering Physics) Shaohua Wang (China Academy of Engineering Physics)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제49권 제4호

발행연도: 2017.6

수록면: 734 - 743 (10page)

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In order to investigate the swelling behavior and fuelecladding interaction mechanism ofUe10Zr alloy metallic fuel at very low burnup, an irradiation experiment was conciselydesigned and conducted on the China Mianyang Research Reactor. Two types of irradiationsamples were designed for studying free swelling without restraint and the fuelecladdinginteraction mechanism. A new bonding material, namely, pure aluminum powder, wasused to fill the gap between the fuel slug and sample shell for reducing thermal resistanceand allowing the expansion of the fuel slug. In this paper, the concise irradiation rig designis introduced, and the neutronic and thermalehydraulic analyses, which were carried outmainly using MCNP (Monte Carlo N-Particle) and FLUENT codes, are presented. Out-of-piletests were conducted prior to irradiation to verify the manufacturing quality and hydraulicperformance of the rig. Nondestructive postirradiation examinations using cold neutronradiography technology were conducted to check fuel cladding integrity and swellingbehavior. The results of the preliminary examinations confirmed the safety and effectivenessof the design.

#CMRR #Irradiation Design #Neutron Radiography #Swelling #U-10Zr

참고문헌 (20)

참고문헌 신청

H. Tsai / 1994 / Irradiation performance of U-Pu-Zr metal fuels for liquid-metal-cooled reactors

D. R. Pedersen / 1992 / Metal fuel manufacturing and irradiation performance / Presented at the American Power Conference

E. R. Cramer / 1989 / In situ observation of axial irradiation growth in liquid-metal reactor metal fuel / Presented at the 1989 Winter Meeting of the American Nuclear Society

C. Nam / 1998 / Statistical failure analysis of metallic Ue10Zr/HT9 fast reactor fuel pin by considering the Weibull distribution and cumulative damage fraction / Ann. Nucl. Energy 25:1441~1453

M. Li / 2012 / Preliminary design of hybrid energy reactor and integral neutron experiments / Fusion Eng. Des 87:1420~1424

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