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Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors

โœ Scribed by Rizwan Ahmed; Aslam; Nasir Ahmad; Mohammad Javed Khan; Mujahid Tanvir


Book ID
108246322
Publisher
Elsevier Science
Year
2007
Tongue
English
Weight
161 KB
Volume
49
Category
Article
ISSN
0149-1970

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A study of reduction in fuel requirement
โœ Rizwan Ahmed; Aslam; Nasir Ahmad; Mohammad Javed Khan; Abdul Manan ๐Ÿ“‚ Article ๐Ÿ“… 2007 ๐Ÿ› Elsevier Science ๐ŸŒ English โš– 170 KB

Pakistan Research Reactor-1 (PARR-1) is a typical swimming pool type MTR utilizing low enriched uranium (19.99% in 235 U) silicide dispersion fuel of density 3.28 gU/cm 3 . The benefits of loading available and upcoming higher density fuels in the existing PARR-1 core have been explored in this stud