Хансен Луиза Ф.
Обсуждаются требования к уточненным расчетам радиационной защиты, обеспечивающей безопасную транспортировку контейнеров с компонентами ядерных боеголовок, специальными сборками и радиоактивными материалами. Делается вывод о необходимости: а) наличия детальной информации о геометрии и композиции материалов контейнера и радиоактивной загрузки; б) точного представления дифференциального энергетического спектра нейтронов и фотонов, выходящих из радиоактивных материалов в контейнере; в) наличия тестированных библиотек нейтронных и фотонных сечений; г) использования точных трехмерных кодов по методу Монте-Карло. Приведено краткое обсуждение необходимости надежных дозиметрических измерений.
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4. Design Guide for Packaging and Off-Site Transportation of Nuclear Compounds, Special Assemblies, and Radioactive Materials. Associated with the Nuclear Explosives and Weapon Safety Program, DOE ALSD5670.12, SG100 Rev. 0, March 2, 1994.
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II. Part I. Chapter 7, CCC-545, Radiation Shielding Information Center, Oak Ridge National Laboratory, O.O. Box 2008, Oak Ridge, TN 37831-6362 (1990).
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10. T.P. Wilcox, Jr. and E.M. Lent, COG-A ParticleTransport Code Designed to Solve the Bolzmann Equation for Deep-Penetration (Shielding) Problems, M-221-1, LLNL, February 1989.
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12. MCNP: Photon Benchmark Problems, LA-12196. UC-705, September 1991. MCNP: Neutron Benchmark Problems, LA-12212. UC-705and UC-704. November 1991.
13. ENDF/B Summary Documentation, ENDF-201, NNDC, BNL, Version V (1987) and Version VI (1990).
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15. American National Standard Institute ANSVANS-6.1.1, January 1977.
