344
Radioprotection et ingénierie nucléaire
Rief H. (1984) Generalized Monte Carlo Perturbation Algorithms for Correlated Sampling
and Second-Order Taylor Series Approach, Annals of Nuclear Energy, 11 (9), 455-476.
Rief H., Dubi A., Elprin T. (1984) Track Length Estimation Applied to Point Detectors,
Nuclear Science and Engineering, 87, 59-71.
Riley M.E., MacCallum C.J., Biggs F. (1975) Electron-Atom Elastic Scattering, Atomic Data
and Nuclear Data Tables, 15, 443.
Rockwell R. III ed. (1956) Reactor shielding design manual (McGraw Hill Compagny Inc.),
chap. 8, pp. 261-344, chap. 9, pp. 346-425.
Rockwell R. III ed. (1956) Reactor shielding design manual, (McGraw Hill Compagny Inc.),
chap. 9, pp. 346-425 ; chap. 10, pp. 427-465.
Rubinstein R.Y. (1981) Simulation and the Monte Carlo Method, , Coll. Wiley Series in
Probability and Mathematical Statistics (New York, John Wiley & Sons).
Sanchez R., McCormick N.J. (1982) A Review of Neutron Transport Approximation,
Nuclear Science and Engineering, 80, 481.
Smith D.L. (1991) Probability, Statistics, and Nuclear Uncertainties in Nuclear Science and
Technology, vol. 4 (OECD Nuclear Energy Agency, Nuclear Data Commitee Series,
Neutron Physics and Nuclear Data in Science and Technology).
Spanier J. (1959) Monte Carlo Methods and their Application to Neutron Transport
Problems, WAPD-195, AEC Research and Development Report, Bettis Atomic Power
Laboratory (Pittsburgh, Pennsylvanie, USA).
Spanier J., Gelbard E.M. (1969) Monte Carlo Principles and Neutron Transport Problems
(USA, Addison-Wesley Publishing Company).
Streaming Calculations using the Point-Kernel Code RANKERN.
Suteau C., Chiron M., Arnaud G. (2004) Improvement of the MERCURE-6’s General
Formalism for Calculating γ-Ray Buildup Factors in Multilayer Shields, Nuclear Science
and Engineering, 147, 43-55.
Suteau C., Chiron M., Arnaud G. (2004) Improvement of the MERCURE-6’s General
Formalism for Calculating γ-Ray Buildup Factors in Multilayer Shields, Nuclear Science
and Engineering, 147, 43-55.
Thomassin A. (1990) Étude des fuites de particules neutres dans les milieux lacunaires pour
l’accélération des méthodes de Monte Carlo, Thèse de doctorat, Université Paris 6.
Vergnaud Th. (2000) Travaux pratiques d’initiation à la méthode de Monte Carlo à l’aide
du code TRIPOLI-4. Cours Génie Atomique.
von Neumann J., Ulam S., Bulletin AMS, Abstract 51-9-165, 1945.
Vukolov V.A., Chukreev F.E. (1991) Tables of recommended standard data, IAEA documentation, INDCC (CCP) – 331.
www.sercoassurance.com/answers/resource/pdfs/paprank.pdf
Zheng S.H., Vergnaud Th. Nimal J.C. (1998) Neutron Cross Section Probability Tables in
Tripoli-3 Monte Carlo Transport Code, Nuclear Science and Engineering, 128,
321-328.
Ziegler F.J. (1977) Helium stopping power and range in all elemental matter, vol. 4,
(Pergamon Press).
Radioprotection et ingénierie nucléaire
Rief H. (1984) Generalized Monte Carlo Perturbation Algorithms for Correlated Sampling
and Second-Order Taylor Series Approach, Annals of Nuclear Energy, 11 (9), 455-476.
Rief H., Dubi A., Elprin T. (1984) Track Length Estimation Applied to Point Detectors,
Nuclear Science and Engineering, 87, 59-71.
Riley M.E., MacCallum C.J., Biggs F. (1975) Electron-Atom Elastic Scattering, Atomic Data
and Nuclear Data Tables, 15, 443.
Rockwell R. III ed. (1956) Reactor shielding design manual (McGraw Hill Compagny Inc.),
chap. 8, pp. 261-344, chap. 9, pp. 346-425.
Rockwell R. III ed. (1956) Reactor shielding design manual, (McGraw Hill Compagny Inc.),
chap. 9, pp. 346-425 ; chap. 10, pp. 427-465.
Rubinstein R.Y. (1981) Simulation and the Monte Carlo Method, , Coll. Wiley Series in
Probability and Mathematical Statistics (New York, John Wiley & Sons).
Sanchez R., McCormick N.J. (1982) A Review of Neutron Transport Approximation,
Nuclear Science and Engineering, 80, 481.
Smith D.L. (1991) Probability, Statistics, and Nuclear Uncertainties in Nuclear Science and
Technology, vol. 4 (OECD Nuclear Energy Agency, Nuclear Data Commitee Series,
Neutron Physics and Nuclear Data in Science and Technology).
Spanier J. (1959) Monte Carlo Methods and their Application to Neutron Transport
Problems, WAPD-195, AEC Research and Development Report, Bettis Atomic Power
Laboratory (Pittsburgh, Pennsylvanie, USA).
Spanier J., Gelbard E.M. (1969) Monte Carlo Principles and Neutron Transport Problems
(USA, Addison-Wesley Publishing Company).
Streaming Calculations using the Point-Kernel Code RANKERN.
Suteau C., Chiron M., Arnaud G. (2004) Improvement of the MERCURE-6’s General
Formalism for Calculating γ-Ray Buildup Factors in Multilayer Shields, Nuclear Science
and Engineering, 147, 43-55.
Suteau C., Chiron M., Arnaud G. (2004) Improvement of the MERCURE-6’s General
Formalism for Calculating γ-Ray Buildup Factors in Multilayer Shields, Nuclear Science
and Engineering, 147, 43-55.
Thomassin A. (1990) Étude des fuites de particules neutres dans les milieux lacunaires pour
l’accélération des méthodes de Monte Carlo, Thèse de doctorat, Université Paris 6.
Vergnaud Th. (2000) Travaux pratiques d’initiation à la méthode de Monte Carlo à l’aide
du code TRIPOLI-4. Cours Génie Atomique.
von Neumann J., Ulam S., Bulletin AMS, Abstract 51-9-165, 1945.
Vukolov V.A., Chukreev F.E. (1991) Tables of recommended standard data, IAEA documentation, INDCC (CCP) – 331.
www.sercoassurance.com/answers/resource/pdfs/paprank.pdf
Zheng S.H., Vergnaud Th. Nimal J.C. (1998) Neutron Cross Section Probability Tables in
Tripoli-3 Monte Carlo Transport Code, Nuclear Science and Engineering, 128,
321-328.
Ziegler F.J. (1977) Helium stopping power and range in all elemental matter, vol. 4,
(Pergamon Press).