Report on intermediate results of the IAEA CRP on 'studies of advanced reactor technology options for effective incineration of radioactive waste'

W. Maschek, A. Stanculescu, B. Arien, Y. Bai, Ch Chabert, A. A. Chebeskov, X. Chen, D. F. Da Cruz, V. Dekoussar, K. Devan, S. Dulla, V. Gopalakrishnan, O. Feynberg, R. Harish, V. Ignatiev, J. Kópházi, J. Li, E. Malambu, P. Mohanakrishnan, K. MoritaG. Pandikumar, Y. Peneliau, P. Ravetto, A. Rineiski, M. Schikorr, R. Srivenkatesan, V. Subbotin, A. Surenkov, M. Szieberth, S. Taczanowski, K. Tuček, P. Vertes, M. Vorotyntsev, J. Uhlíř, H. Wider, Y. Wu, R. Zakirov, S. Zheng

研究成果: 書籍/レポート タイプへの寄稿会議への寄与

抄録

In 2003 the IAEA has initiated a Coordinated Research Project (CRP) on "Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste". Major intermediate results have been obtained and will be reported here. The overall objective of the CRP, performed within the framework of IAEA's Nuclear Energy's Department Technical Working Group on Fast Reactors, is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. Sixteen institutions from 12 member states and one international organization participated in this CRP. The CRP concentrated on the assessment of the dynamic behaviour of various transmutation systems. The reactor systems investigated comprise critical reactors, subcritical accelerator driven systems with heavy liquid metal and gas cooling, critical molten salt systems and hybride fusion/fission systems. Both fertile and fertile-free fuel options have been investigated. For a deep assessment of the transient and safety behaviour, the analytical capabilities have to be qualified. A major effort of the CRP consisted in the benchmarking of steady state core configurations and performing transient/accident simulations. For a general assessment and comparison, the safety coefficients were determined for the individual systems. In a second step transient analyses were performed which reflected the generic behaviour of the various reactors types. In addition the transmutation potential, burn-up behaviour and decay heat of minor actinide bearing fuels were investigated.

本文言語英語
ホスト出版物のタイトル13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
ページ598-610
ページ数13
出版ステータス出版済み - 2007
イベント13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007 - Istanbul, トルコ
継続期間: 6月 3 20076月 8 2007

出版物シリーズ

名前13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
2

その他

その他13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
国/地域トルコ
CityIstanbul
Period6/3/076/8/07

!!!All Science Journal Classification (ASJC) codes

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学

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