Analysis of the three-dimensional VENUS-2 MOX core benchmark using the Monte Carlo code TRIPOLI-4 and the ENDF/B-VI.4, ENDF/B-VII.0 and JEFF-3.1 nuclear data sets von Savva, P., Varvayanni, M., Catsaros, N.

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Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum von Huot-Marchand, C., Colin, C., Varvayanni, M., Savva, P., Chrysanthopoulou, N., Catsaros, N.

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Compilation of Existing Neutron Screen Technology von Catsaros, N., Varvayanni, M., Savva, P., Chrysanthopoulou, N.

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Testing the new stochastic neutronic code ANET in simulating safety important parameters von Xenofontos, T., Delipei, G.-K., Savva, P., Varvayanni, M., Maillard, J., Silva, J., Catsaros, N.

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Dependence of control rod worth on fuel burnup von Savva, P., Varvayanni, M., Catsaros, N.

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Control rod worth calculations using deterministic and stochastic methods von Varvayanni, M., Savva, P., Catsaros, N.

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Investigating the breeding capabilities of hybrid soliton reactors von Catsaros, N., Gaveau, B., Jaekel, M.-T., Jejcic, A., Maillard, J., Maurel, G., Savva, P., Silva, J., Varvayanni, M., Xenofontos, T.

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Aspects of cell calculations in deterministic reactor core analysis von Varvayanni, M., Savva, P., Catsaros, N.

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Effect of Reactor Fuel Enrichment on Gamma Heating of Irradiated Samples von Varvayanni, M., Savva, P., Catsaros, N., Antonopoulos-Domis, M.

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A Newton-based Jacobian-free approach for neutronic-Monte Carlo/thermal-hydraulic static coupled analysis von Mylonakis, Antonios G., Varvayanni, M., Catsaros, N.

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Building a dynamic code to simulate new reactor concepts von Catsaros, N., Gaveau, B., Jaekel, M.-T., Maillard, J., Maurel, G., Savva, P., Silva, J., Varvayanni, M.

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Homogeneous zones definition in deterministic codes and effect on computed neutronic parameters von Varvayanni, M., Savva, P., Catsaros, N., Antonopoulos-Domis, M.

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Estimation of irradiated control rod worth von Varvayanni, M., Catsaros, N., Antonopoulos-Domis, M.

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A point kernel model for the energy deposited on samples from gamma radiation in a research reactor core von Varvayanni, M., Catsaros, N., Antonopoulos-Domis, M.

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Evaluation of nuclear heating of small samples in a research reactor core von Varvayanni, M., Catsaros, N., Antonopoulos-Domis, M.

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Multi-physics and multi-scale methods used in nuclear reactor analysis von Mylonakis, A.G., Varvayanni, M., Catsaros, N., Savva, P., Grigoriadis, D.G.E.

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Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis von Mylonakis, Antonios G., Varvayanni, M., Grigoriadis, D.G.E., Catsaros, N.

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Void induced reactivity in a mixed MTR core von Varvayanni, M., Stakakis, E., Catsaros, N., Antonopoulos-Domis, M.

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Assessment of off-site early countermeasures in the event of a LOCA in a research reactor von Pappas, C., Ikonomopoulos, A., Sfetsos, A., Andronopoulos, S., Aneziris, O., Varvayanni, M., Catsaros, N.

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Air and vegetated ground interactions in air quality diagnosis for emergency response von Varvayanni, M, Davakis, E, Catsaros, N

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