고연소도 경수로 사용후핵연료의 열처리에 따른 세슘 방출거동

Cesium Release Behavior during the Themal Treatment of High Burn-up Spent PWR Fuel

Geun IL Park, Kwang Hun Cho, Jung Won Lee, Jang Jin Park, Myung Seung Yang, Kee Chan Song

Abstract

The dynamic release behavior of Cs from high burn-up spent PWR fuel was experimentally performed under the conditions of a thermal treatment process such as voloxidation and sintering conditions. In voloxidation process, influence of the oxidation and reduction atmosphere on the Cs release characteristic using fragment type of spent fuel heated up to was compared. In sintering process, temperature history effect on Cs release behavior was evaluated using green pellet under 4% environment. Temperature range for complete Cs release from spent fuel fragment under voloxidation condition was about , but that of green pellet under the reduction atmosphere was . Key parameters on Cs release behavior from spent fuel was powder formation as well as the diffusion rate of Cs compound to grain boundary and fuel surface.

Key Words : DUPIC, Spent fuel, Green pellet, Voloxidation, Sintering, Semi-volatile fission product, Cesium, Fractional release percent, 듀픽, 사용후핵연료.압분체, 휘발성 산화, 소결, 준휘발성 핵분열생성물, 세슘, 방출분율

Reference

JNFCWT

Online Submission

Korean Radioactive
Waste Society (KRS)

Editorial Office
Contact Information

- Tel: +82-42-861-5851, 866-4157
- Fax: +82-42-861-5852
- E-mail: krs@krs.or.kr

SITE MAP