Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor

Author:

Alqahtani M.,Buijs A.,Day S.E.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes;Amin;Rad. Phys. Chem.,2017

2. Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor;Aldawahrah;Results Phys.,2018

3. Calculation of fuel burnup and radionuclide inventory in the Syrian miniature neutron source reactor using the GETERA code;Khattab;Ann. Nucl. Energy,2011

4. Calculation of fuel burnup and radionuclide inventory in the 10MW MTR type research reactor using the GETERA code;Dawahra;Ann. Nucl. Energy,2015

5. Calculation of fuel burnup and radioactive inventory in the CANDU reactor using the GETERA and MCNP4C codes;Dawahra;Int. J. Nucl. Energy Sci. Technol.,2015

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