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Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process

  • Published:2021-06 Issue:6 Volume:53 Page:2019-2024
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

Lee ChoongWie,Kim Hee Reyoung,Lee Seung Jun

Funder

National Research Foundation of Korea

Korea Institute of Energy Technology Evaluation and Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. A qualitative identification and analysis of hazards, risks and operating procedures for a decommissioning safety assessment of a nuclear research reactor;Jeong;Ann. Nucl. Energy,2008

2. Visualization of a dismantling environment for an evaluation of a worker’s dose during the decommissioning of KRR-1&2;Park;Ann. Nucl. Energy,2008

3. The preliminary 3D dynamic simulation on the RSR dismantling process of the KRR-1&2;Kim;Ann. Nucl. Energy,2003

4. Methods for the Minimization of Radioactive Waste from Decontamination and Decommissioning of Nuclear Facilities,2001

5. Inventory of Information for the Identification of Guiding Principles in the Decommissioning of Nuclear Installations;Crégut,1991

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