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  1. 1
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    The code system SSYST, present status and current development.

    Published 1984.
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  2. 2
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    Development of the computer code system for the analyses of PWR core.

    Published 1992.
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  3. 3
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    The code system S SYST, present status and current development..

    Published 1984.
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  4. 4
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    Development of BERMUDA;A radiation transport code system part I.Neutron transport codes.

    Published 1992.
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  5. 5
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    Development of Bermuda; a radiation transport code system part II. Gamma rays transport codes. by Suzuki, T.

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  6. 6
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    Development of Bermuda: A radiation transport code system part III a one-dimensional adjoint neutron transport code. by Suzuki, Tomoo

    Published 1994.
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  7. 7
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    Final report on code development [DOSEEX] and dose calculations in the frame of ITER for the tear 1994. by Meyer, D.

    Published 1995.
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  8. 8
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    Numerical experiments in finite element analysis of thermoelastoplastic behaviour of materials. Further developments of the PLASTEF code. by Basombrío, F. G., Sánchez Sarmiento, G.

    Published 1980
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  9. 9
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    Development of analysis code for thermal hydrodynamics of marine reactor under multi-dimensional ship motions, retran-02/GRAV.

    Published 1992.
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  10. 10
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    ACI CODE-349-13 :

    Published 2014
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  11. 11
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    Analysis of experimental data on neutron-induced reactions and development of code pcross for the calculation of differential pre-equilibrium emission spectra with modelling of level density function.

    Published [s.f.].
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  12. 12
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    Thermal and mechanical response of steel sheets welded by laser process: preanalysis made by abaqus code: Conclusive report on the work developed in the frame of the FASP-EUREKA project [EU353], 1992-1994. by Carmignani, Bruno

    Published 1994.
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  13. 13
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    In-core fuel management programs for nuclear power reactors: Final report of the co-ordinated research programme on codes adaptable to small or medium size computers in developing countries for in-core fuel management organized by the International Atomic Energy Agency.

    Published 1984.
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  14. 14
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    Desarrollo de un modelo de una fuente fría de neutrones para el Reactor RA-6 by Gustinelli, Huilén

    Published 2023
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  15. 15
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    Desarrollo, verificación y validación de algoritmo de cálculo de Beta efectivo para la línea de cálculo CONDOR-CITVAP by Olivares, Darián A.

    Published 2022
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  16. 16
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    Desarrollo de un código de centro de giro para estudio de transporte en reactores de fusión nuclear by Gallo Claussi, Agustín

    Published 2023
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  17. 17
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    Desarrollo de una biblioteca de trabajos de datos nucleares. by Fabisik, Juan J.

    Published 2014
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  18. 18
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    Water hammer in pipeline systems. by Záruba, Josef

    Published 1993.
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  19. 19
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    Desarrollo y simulación de alta resolución de un modelo simplificado de corrientes de turbidez by Trono Figueras, Renato

    Published 2022
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  20. 20
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    Análisis de datos y desarrollo de modelos de cálculo neutrónico para sistemas híbridos, ADS. by Cintas, Ana

    Published 2013
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