Υπολογιστικοί Κώδικες Πυρηνικής Τεχνολογίας
Ανάλυση Πυρηνικών Αντιδραστήρων
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ORIGEN-2.2 |
Isotope Generation and Depletion Code of Nuclear Fission Reactor Fuels and Wastes |
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SCALE- 4.4 A |
Criticality, Shielding, Heat Transfer, Fuel Depletion |
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MCNPX |
Criticality, ADS |
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CITATION |
Criticality |
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MELT-3 |
FR core analysis |
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EUREKA |
Core analysis |
Ραδιολογικές επιπτώσεις από ατυχήματα σε πυρηνικούς αντιδραστήρες
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RASCAL 3.0.3 |
Radiological Doses from Accidental Release to Atmosphere |
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ResRad |
Evaluation of Human Health Risk at sites contaminated with radioactivity |
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TACS-5 |
Radioactivity release to the environment in reactor accident |
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ORION-II |
Radioactivity release to the environment in reactor accident |
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Hot Spot |
Evaluating incidents involving radioactive material |
Διάχυση ακτινοβολίας, Θωράκιση
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MCNPX 2.5.0. |
Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications. |
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PUDOL |
Dosimetry and Shielding in the fabrication of MOX- and Minor Actinide containing- nuclear fuels |
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ALICE |
Charged Particle Transport |
Αξιολόγηση ρίσκου ατυχήματος σε αντιδραστήρες
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PSA |
Probabilistic Safety Assessment of nuclear reactors |
Φασματοσκοπία-γ
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SOLID |
Monte Carlo Calculation of the Solid Angle subtended between bare/collimated detectors and 3D gamma emitting objects |
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GENIE 2000 |
γ- spectroscopy software |
Εκπαίδευση στην Πυρηνική Τεχνολογία
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PWR & BWR simulators VPI-NECM NUCLEAR TECHNOLOGY |
Simulating operation, accidents for PWR & BWRNuclear Engineering Program Collection for university trainingDemonstration of various aspects of a nuclear fuel cycle |