| 학회 |
한국재료학회 |
| 학술대회 |
2007년 봄 (05/10 ~ 05/11, 무주리조트) |
| 권호 |
13권 1호 |
| 발표분야 |
에너지 환경재료 |
| 제목 |
Corrosion Characteristics of 316L, HT-9 and T91 at 570oC Flowing Liquid Lead-alloy |
| 초록 |
KAERI(Korea Atomic Energy Research Institute) has been developing future nuclear reator systems adopting lead-alloys as reactor coolants. One example is HYPER which is designed to transmute long-lived transuranic actinides and fission products such as Tc-99 and I-129. Pb-Bi is used as core coolant and target material for HYPER. Another example is a GEN-IV type lead cooled fast reactor. Both lead and lead-bismuth have a corrosion problem at high temperature. KAERI built corrosion test loops to study corrosion behaviour of reactor structure materials which are steels such as 316L, T91 and HT-9. HT-9 is the candidate material for fuel cladding. T91 is the candidate material for HYPER beam window. The test loops are named as KPAL-I (KAERI Pb-Alloy Loop I) and KPAL-II for Pb-Bi and Pb loops respectively. The experiment was performed under oxygen-controlled atmospheres at 570oC. Oxygen concentration was controlled by adjusting H2 and H2O vapor ratio. Controlled oxygen can make oxide layer to protect samples against the corrosion. |
| 저자 |
송태영, 조충호, 조춘호
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| 소속 |
한국원자력(연) |
| 키워드 |
납합금; 부식; 원자로; 냉각재
|
| E-Mail |
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