Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code-Reference-Cited by-同舟云学术

Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code

Published:2021-12 Issue: Volume:142 Page:104012
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Reda Sonia M.,Saleh Hosam M.^ORCID

Publisher

Elsevier BV

Subject

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

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4. Solidification of hot real radioactive liquid scintillator waste using cement–clay composite;Bayoumi;Monatshefte für Chemie-Chemical Mon.,2013

5. Overview of environmental pollution and clean management of heavy metals and radionuclides by using microcrystalline cellulose;Dawoud;J. Nucl. Ene Sci. Power Gener. Technol.,2021

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