cBN 입자상 강화재 첨가에 따른 중성자 흡수용 B4C/Al 복합재의 열전도도 변화 연구
Improving thermal conductivity of neutron absorbing B4C/Al composites by introducing cBN reinforcement
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초록
본 연구에서는 기존 사용후핵연료 운송/저장 용기에 사용되는 중성자 흡수용 B4C/Al 복합소재의 열전도도를 개선하기 위해 탄화붕소(B4C)와 입방정 질화붕소(cBN)를 동시에 강화재로 사용한 알루미늄(Al) 기지 복합소재를 제조 평가하였다. 이를 위해서 교반주조 공정을 통해 복합재 잉곳을 제조하고 이를 압연하여 실용이 가능한 중성자 흡수용 소재를 성공적으로 제조하였다. 제조된 소재의 평가를 위해 cBN 첨가에 따른 열전도도와 중성자 흡수능 변화를 관찰하였다. 열전도도 측정 결과, B4C 단일 입자만을 사용한 복합소재 대비 B4C, cBN을 함께 사용한 복합소재가 동일 체적율 조건 하에서 약 3%의 열전도도 증가가 발생하는 것을 확인하였으며 중성자 흡수 단면적 계산을 통해 중성자 흡수능이 무시할 수 있는 수준으로 저하가 발생하는 것을 확인하였다. 본 연구의 결과를 바탕으로, 중성자 흡수 소재의 새로운 설계 방안을 제시하고 고성능 운송/저장 용기의 개발에 기여할 수 있을 것으로 기대된다.
Abstract
This study aimed to enhance the thermal conductivity of B4C/Al composite materials, commonly used in transport/storage containers for spent nuclear fuel, by incorporating both boron carbide (B4C) and cubic boron nitride(cBN) as reinforcing agents in an aluminum (Al) matrix. The composite materials were successfully manufactured through a stir casting process and practical neutron-absorbing materials were obtained by rolling the fabricated composite ingot. The evaluation of the thermal conductivity of the fabricated composites was carried out because thermal conductivity is critical for neutron absorbing materials. The thermal conductivity measurement results indicated an approximately 3% increase in thermal conductivity under the same volume fraction when compared to composite materials using only B4C particles. Through neutron absorption cross-sectional area calculations, it was confirmed that the neutron absorption capability decreased to a negligible level. Based on the findings of this study, new design approaches for neutron absorption materials are proposed, contributing to the development of high-performance transport/storage containers.
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