Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for calculations of neutronic parameters

Author:

Jaradat Mustafa K.,Radulović Vladimir,Park Chang Je,Snoj Luka,Alkhafaji Salih M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Burnup estimation for plate type fuel assembly of research reactors through the least square fitting method;Alawneh;Ann. Nucl. Energy,2014

2. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology;Chadwick;Nucl. Data Sheets,2006

3. Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR;Conlin;Trans. Am. Nucl. Soc.,2005

4. Initial MCNP6 Release Overview – MCNP6 version 1.0;Goorley,2013

5. JRTR Initial Criticality Calculations and Nuclear Commissioning Tests;Jaradat,2015

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