A capsule is the device for irradiation test of nuclear materials and fuels in HANARO. The instrumentation cables are sealed tightly by brazing at the top of the capsule. In this study, the integrities at the brazing of both Inconel 600 and STS 310 materials were confirmed by tensile test, survey of damage on coating, and measurement of insulation resistance. At tensile test, brazing areas were not damaged but the thermocouples themselves were broken on both the materials. At flame heat test, the coating of STS 310 material was maintained without damage but the brittle fracture on Inconel 600 material was observed. Insulation resistances were confirmed to be satisfactory in case of both the materials. In this analysis, the thermocouple was expanded by 0.81mm on the direction of y-axis and the tube was contracted by 0.57mm on the direction of x-axis. As the result, cracks might be occurred with thermal stresses. EDX spectrum analysis showed that the BAg-1 filler metal formed a thin reaction layer on the surface of brazed metal.

The irradiation tests of materials in HANARO have been performed usually at temperatures below 300℃ at which the RPV(Reactor Pressure Vessel) materials of the commercial reactors such as the light water reactor and CANDU are operated. As VHTR(Very High Temperature Reactor) and SFR (Sodium-cooled Fast Reactor) projects are being carried as a part of the present Gen-IV program in Korea, the requirements for irradiation of materials at temperatures higher than 500℃ are recently being gradually increased. To overcome the restriction in the use at high temperature of the existing Al thermal media, a new capsule with double thermal media composed of two kinds of materials such as Al-Ti and Al- graphite was designed and fabricated more advanced than the single thermal media capsule. At the irradiation test of the capsule, the temperature of the specimens successfully reached 700℃ and the integrity of Al, Ti and graphite material was maintained.

400˚C H2O, D2O및 O2분위기에서 Zr-2.5Nb합금의 부식거동을 분석하였다. Martensitic α'-Zr상이나 α-Zr과 β-Zr상의 Zr-2.5Nb합금인 경우, 부식분위기에 매우 민감하여, O2속에서 가장 큰 부식속도를 보였다. 반면, α-Zr나 β-Zr상의 경우, 부식 매질에 따른 별다른 차이없이 높은 부식저항성을 보였다. 이러한 Zr-2.5Nb 합금의 미세조직 및 부식 매질에 따른 부식거동변화는 Zr-2.5Nb 합금의 음극 지배 부식반응의 관점으로 해석되었으며, 이들 결과를 이용하여 CANDU 형및 RBMK 형 Zr-2.5Nb 압력관의 가동조건 차이를 설명할 수 있었다. Zr-2.5Nb 합금의 모든 조직에서 주로 단사정 ZrO2산화물이 형성되었으며, 산화물내 정방정 ZrO2비율은 산화물 두께가 증가함에 따라 감소하였다.