| 학회 | 한국재료학회 |
| 학술대회 | 2005년 봄 (05/26 ~ 05/27, 무주리조트) |
| 권호 | 11권 1호 |
| 발표분야 | 에너지환경재료 |
| 제목 | Zr함량 변화에 따른 합금형 U-Zr연료와 HT9 피복재의 계면반응 |
| 초록 | 1. Introduction Blanket fuel assembly contains a bundle of 331 pins arrayed in triangular pitch which has hexagonal bundle structure. TRU(transuranic)-Zr alloy fuel is considered as a blanket fuel for HYPER (Hybrid Powder Extraction Reactor). In alloy type TRU-Zr fuel, the blanket fuel slug is immersed in lead for thermal bonding with the cladding. The blanket fuel cladding material is ferritic-martensitic steel HT9. During irradiation, fuels swell and come into contact with the cladding, then metallurgical reaction at the fuel-cladding interface occurs and affects the integrity of the cladding. The reaction between the fuel and the Fe-base cladding materials should be well understood in order to evacuate the fuel performance. Several studies were conducted on the reactions between U-Zr or U-Pu-Zr alloys and stainless steels. We fabricated U-xZr fuel(x=55,59.5,64wt%) instead of the actual (TRU-10wt%Zr)-Zr fuel for HYPER. This study investigates the solid-states reaction layers formed at 700oC at diffusion interfaces: alloy type U-Zr fuel/HT9 according to concentration of Zr. 2. Experimental procedure The alloy type U-xZr(x=55, 59.5, 64wt%) fuels were fabricated by mixing, pressing, sintering and extrusion. The cladding steel in this investigation is stainless steel HT9. Both fuel and cladding steel were cut into disks about 2mm thick. Each of the diffusion couple assemblies was encapsulate in a quartz tube. The diffusion couples were annealed isothermally at 700oC. The alloy type U-Zr fuel/HT9 couples were annealed at 700oC for 100 h. After completion of the diffusion anneal, the couples were quenched in water, then sectioned parallel to the diffusion direction. The sectioned couple was embedded in epoxy resin and then the cross-sectional surface was polished with 3㎛ diamond paste for SEM. The reaction layer thickness and concentration distributions of diffusion reaction layer were measured by SEM equipped with EDAX. 3. Result and discussion In U-Zr fuel/HT9 couple, the U in the fuel diffuses into HT9 cladding material with below 1㎛ reaction layer. The elemental Fe in cladding material diffuses into the fuel core and then forms reaction layer of about 2㎛. |
| 저자 | 이봉상, 박원석, 송태영 |
| 소속 | 한국원자력(연) |
| 키워드 | metallic fuel; interfacial reaction; powder metallurgy |
