Removal of 90Sr from highly Na+-rich liquid nuclear waste with a layered vanadosilicate-Reference-Cited by-同舟云学术

Removal of 90Sr from highly Na+-rich liquid nuclear waste with a layered vanadosilicate

Published:2019 Issue:6 Volume:12 Page:1857-1865
ISSN:1754-5692
Container-title:Energy & Environmental Science
language:en
Short-container-title:Energy Environ. Sci.

Author:

Datta Shuvo Jit¹²³⁴⁵,Oleynikov Peter⁶⁷⁸⁹,Moon Won Kyung¹²³⁴⁵,Ma Yanhang⁶⁷⁸⁹,Mayoral Alvaro⁶⁷⁸⁹^ORCID,Kim Hyuncheol¹⁰¹¹¹²⁵^ORCID,Dejoie Catherine¹³¹⁴¹⁵,Song Mee Kyung¹²³⁴⁵,Terasaki Osamu⁶⁷⁸⁹¹⁶^ORCID,Yoon Kyung Byung¹²³⁴⁵^ORCID

Affiliation:

1. Korea Center for Artificial Photosynthesis

2. Department of Chemistry

3. Sogang University

4. Seoul 04107

5. South Korea

6. School of Physical Science and Technology

7. Shanghai Tech University

8. Shanghai 201210

9. China

10. Environmental Radioactivity Assessment Team

11. Korea Atomic Energy Research Institute

12. Daejeon

13. European Synchrotron Radiation Facility

14. Grenoble 38043

15. France

16. Department Materials and Environmental Chemistry

Abstract

Capture of trace amounts (parts per trillion or ppt level) of ⁹⁰Sr from highly Na⁺-rich (5 M or 115 000 parts per million) liquid wastes produced from reprocessing of spent nuclear fuel rods is crucial for continuous operation of nuclear power plants.

Funder

Sogang University

Ministry of Science, ICT and Future Planning

Recruitment Program of Global Experts

Science and Technology Commission of Shanghai Municipality

China Association for Science and Technology

National Natural Science Foundation of China

Publisher

Royal Society of Chemistry (RSC)

Subject

Pollution,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment,Environmental Chemistry

Link

http://pubs.rsc.org/en/content/articlepdf/2019/EE/C8EE03302A

Reference36 articles.

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3. Treatment and Recycling of Spent Nuclear Fuel , ed. M. Lecomte , CEA , Paris , 2008

4. A. L. Nichols , D. L.Aldama and M.Verpelli , Handbook of Nuclear Data for Safeguards , IAEA , Vienna , 2007

5. Predicting material release during a nuclear reactor accident

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