1 |
N. Xoubi, A.Y. Soliman, Neutronic calculations of the IAEA 10 MW MTR benchmark reactor via finite element method using COMSOL multiphysics code, Ann. Nucl. Energy 109 (2017) 277-283, https://doi.org/10.1016/j.anucene.2017.05.033.
DOI
|
2 |
K.S. Chaudri, S.M. Mirza, Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark, Prog. Nucl. Energy 81 (2015) 43-52, https://doi.org/10.1016/j.pnucene.2014.12.018.
DOI
|
3 |
A. Bousbia-Salah, H. Benkharfia, N. Kriangchaiporn, A. Petruzzi, F. D'Auria, N. Ghazi, MTR benchmark static calculations with MCNP5 code, Ann. Nucl. Energy 35 (2008) 845-855, https://doi.org/10.1016/j.anucene.2007.09.016.
DOI
|
4 |
M. Margulis, Y. Shaposhnik, IAEA 10 MW Th MTR Benchmark Static Calculation with SERPENT Code, 2014.
|
5 |
P.K. Romano, B. Forget, The OpenMC Monte Carlo particle transport code, Ann. Nucl. Energy 51 (2013) 274-281, https://doi.org/10.1016/j.anucene.2012.06.040.
DOI
|
6 |
N. Xoubi, A Computational Model of the High Flux Isotope Reactor - Validation and Application to Low Enriched Uranium Fuels Ned Xoubi, 2008. Fuel.
|
7 |
T. Mahmood, S. Pervez, M. Iqbal, Neutronic analysis for core conversion (HEULEU) of Pakistan research reactor-2 (PARR-2), Ann. Nucl. Energy 35 (2008) 1440-1446, https://doi.org/10.1016/j.anucene.2008.01.012.
DOI
|
8 |
R.A. Schickler, W.R. Marcum, S.R. Reese, Comparison of HEU and LEU neutron spectra in irradiation facilities at the Oregon State TRIGA(R) Reactor, Nucl. Eng. Des. 262 (2013) 340-349, https://doi.org/10.1016/j.nucengdes.2013.05.004.
DOI
|
9 |
I.D. Abdelrazek, E.A. Villarino, ETRR-2 Nuclear Reactor, Facility specification, 2015.
|
10 |
IAEA, IAEA-TECDOC-233 : Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels Guidebook, 1980.
|
11 |
N. Xoubi, Calculation of the power and absolute flux of a source driven subcritical assembly using Monte Carlo MCNP code, Ann. Nucl. Energy 97 (2016) 96-101, https://doi.org/10.1016/J.ANUCENE.2016.07.009.
DOI
|
12 |
N. Xoubi, A.Y. Soliman, Neutronic modeling and calculations of the ETRR-2 MTR reactor using COMSOL multiphysics code, Ann. Nucl. Energy 109 (2017), https://doi.org/10.1016/j.anucene.2017.06.007.
|
13 |
IAEA, Research Reactor Core Conversion Guidebook. TECDOC-643., Vienna, 1991. https://www.iaea.org/publications/899/research-reactor-coreconversion-guidebook-volume-4-fuels-appendices-i-k.
|
14 |
P.K. Romano, N.E. Horelik, B.R. Herman, A.G. Nelson, B. Forget, K. Smith, OpenMC: a state-of-the-art Monte Carlo code for research and development, Ann. Nucl. Energy 82 (2015) 90-97, https://doi.org/10.1016/j.anucene.2014.07.048.
DOI
|
15 |
IAEA-TECDOC-1223, Current Status of Neutron Capture Therapy, 2001.
|
16 |
S. Dawahra, K. Khattab, G. Saba, A comparative study of the neutron flux spectra in the MNSR irradiation sites for the HEU and LEU cores using the MCNP4C code, Appl. Radiat. Isot. 104 (2015) 67-73, https://doi.org/10.1016/j.apradiso.2015.06.006.
DOI
|
17 |
N. Xoubi, A.Y. Soliman, Neutronic calculations of the IAEA 10 MW MTR benchmark reactor via finite element method using COMSOL multiphysics code, Ann. Nucl. Energy 109 (2017), https://doi.org/10.1016/j.anucene.2017.05.033.
|