Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors-Reference-Cited by-同舟云学术

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

Published:2007-04 Issue:3 Volume:49 Page:246-252
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Ahmed Rizwan,Aslam ,Ahmad Nasir,Khan Mohammad Javed,Tanvir Mujahid

Publisher

Elsevier BV

Subject

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

Reference15 articles.

1. Effect of new cross section evaluations on criticality and neutron energy spectrum of a typical material test research reactor;Ahmad;Annals of Nuclear Energy,2004

2. Effect of updated WIMSD libraries on neutron energy spectrum at irradiation site of Pakistan Research Reactor-1 using 3D modeling;Ahmad;Annals of Nuclear Energy,2005

3. Effect of different cross section data set on reflectors of a typical material test research reactor;Ahmad;Progress in Nuclear Energy,2005

4. Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors;Ahmed;Annals of Nuclear Energy,2005

5. Burnup study for Pakistan Research Reactor-1 utilizing high density low enriched uranium fuel;Ahmed;Annals of Nuclear Energy,2005

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Core reduction for increasing neutron flux and radioisotope production in the IEA-R1 research reactor;Nuclear Engineering and Design;2024-05

2. Calculations of Double-Differential Neutron Emission Cross Sections for 9Be Target Nucleus at 14.2 MeV Neutron Energy;Journal of Fusion Energy;2014-12-19

3. Application of coupled code technique to a safety analysis of a standard MTR research reactor;Nuclear Engineering and Design;2009-10

4. Reactivity feedback coefficients of a material test research reactor fueled with high-density U3Si2 dispersion fuels;Nuclear Engineering and Design;2008-10

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