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For: Ahmed R, Aslam, Ahmad N, Khan MJ, Tanvir M. Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors. Progress in Nuclear Energy 2007. [DOI: 10.1016/j.pnucene.2006.12.002] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
Number Cited by Other Article(s)
1
Calculations of Double-Differential Neutron Emission Cross Sections for 9Be Target Nucleus at 14.2 MeV Neutron Energy. JOURNAL OF FUSION ENERGY 2014. [DOI: 10.1007/s10894-014-9823-1] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
2
Hamidouche T, Bousbia-Salah A, Si-Ahmed EK, Mokeddem MY, D’Auria F. Application of coupled code technique to a safety analysis of a standard MTR research reactor. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.06.002] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
3
Reactivity feedback coefficients of a material test research reactor fueled with high-density U3Si2 dispersion fuels. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.05.002] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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