Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1)-Reference-Cited by-同舟云学术

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Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1)

Published:2016-01 Issue: Volume:87 Page:584-590
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ali M. Rizwan,Khan R.,Chaudri K.S.^ORCID,Stummer T.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. A Core Conversion Study by Using Higher Density Low Enriched Uranium Fuels;Ahmad,2006

2. Effect of updated WIMSD libraries on neutron energy spectrum at irradiation site of PARR-1 using 3D modeling;Ahmad;Ann. Nucl. Energy,2005

3. Neutronic Calculations of PARR-1 Cores using LEU-Silicide Fuel;Arshad,1991

4. Thermal Hydraulics and Safety Analyses for Pakistan Research Reactor-1;Bokhari,1999

5. Introduction to Nuclear Reactor Operations;Burn,1986

Cited by 3 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. Implications of Local Scale Meteorological Data on Radioactive Plume Dispersion and Dose Delivery for a Hypothetical Severe Accident at PARR-1;Arabian Journal for Science and Engineering;2022-06-08

2. Monte Carlo modeling of the NUR Nuclear Research Reactor;Progress in Nuclear Energy;2019-03

3. Neutronic modeling and calculations of the ETRR-2 MTR reactor using COMSOL multiphysics code;Annals of Nuclear Energy;2017-11

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