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Simulated studies on optimization and characterization of feed and product of melter for safe disposal of high-level radioactive liquid waste

  • Published:2020-01 Issue: Volume:118 Page:103135
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Selvakumar J.ORCID,Rajasekaran S.,Chitra S.,Paul Biplob

Funder

NRB

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference26 articles.

1. Handbook of Glass Properties;Bansal,1986

2. Temperature distribution within a cold cap during nuclear waste vitrification;Dixon;Environ. Sci. Technol.,2015

3. Glasses in materials sciences in space;Doremus,1986

4. The chemical durability of K2O-CaO-MgO-SiO2 glasses;El-Shamy;Phys. Chem. Glasses,1973

5. Radionuclides containment in nuclear glasses: an overview;Gin;Radiochim. Acta,2017
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