Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code-Reference-Cited by-同舟云学术

Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code

Published:2014-11 Issue: Volume:77 Page:65-71
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Galahom A. Abdelghafar,Bashter I.I.,Aziz Moustafa

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. Neutronic design of hydride fueled BWRs;Fratoni;Nucl. Eng. Des.,2009

2. Design boiling water reactor core model using MCNPX for studying the burnable poisons and the axial enrichment fuel effect on the neutronic characteristics;Galahom;J. Nucl. Eng. Technol.,2013

3. Economic analysis of hydride fueled BWR;Ganda;Nucl. Eng. Des.,2009

4. Core Fuel Management Code Package Validation for BWRs;IAEA TECDOC-849,1995

5. Thorium Based Fuel Options for the Generation of Electricity. Developments in the 1990s;IAEA-TECDOC-1155,2000

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