ЛИТЕРАТУРА К ПРИЛОЖЕНИЮ V

[VII.1] PRUVOST, N.L., PAXTON, H.C., Nuclear Criticality Safety Guide, Rep. LA-12808, Los Alamos National Laboratory, Los Alamos, NM (1996).

[VII.2] THOMAS, J.T., Ed., Nuclear Safety Guide TID-7016, Revision 2, Rep. NUREG/CR-0095 (ORNL/NUREG/CSD-6), US Nuclear Regulatory Commission, Washington, DC (1978).

[VII.4] JAPAN ATOMIC ENERGY RESEARCH INSTITUTE, Nuclear Criticality Safety Handbook (English Translation), JAERI-Review-95-013, JAERI, Tokyo (1995).

[VII.5] AMERICAN NATIONAL STANDARDS INSTITUTE, American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, ANSI/ANS-8.1-1983 (Reaffirmed 1988), American Nuclear Society, LaGrange Park, IL (1983).

[VII.6] AMERICAN NATIONAL STANDARDS INSTITUTE, American National Standard for Nuclear Criticality Control of Special Actinide Elements, ANSI/ANS-8.15-1981, American Nuclear Society, LaGrange Park, IL (1981).

[VII.7] LANDERS, N.F., PETRIE, L.M., "Uncertainties associated with the use of the KENO Monte Carlo criticality codes", Safety Margins in Criticality Safety (Int. Top. Mtg San Francisco, 1989), American Nuclear Society, LaGrange Park, IL (1989) 285.

[VII.8] FORSTER, R.A., et al., "Analyses and visualization of MCNP criticality results", Nuclear Criticality Safety (ICNC'95) (Proc. Int. Conf. Albuquerque, 1995), Vol. 1, Univ. of New Mexico, Albuquerque, NM (1995) 6 - 160.

[VII.9] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Nuclear Energy - Fissile Materials - Principles of Criticality Safety in Storing, Handling, and Processing, ISO-1709, ISO, Geneva (1995).

[VII.10] LICHTENWALTER, J.J., BOWMAN, S.M., DEHART, M.D., Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, Rep. NUREG/CR-6361 (ORNL/TM-13211), US Nuclear Regulatory Commission, Washington, DC (1997).

[VII.11] PARKS, C.V., WRIGHT, R.W., JORDAN, W.C., Adequacy of the 123-Group Cross-Section Library for Criticality Analyses of Water-moderated Uranium Systems, Rep. NUREG/CR-6328 (ORNL/TM-12970), US Nuclear Regulatory Commission, Washington, DC (1995).

[VII.12] PARKS, С.V., JORDAN, W.C., PETRIE, L.M., WRIGHT, R.Q., Use of metal/uranium mixtures to explore data uncertainties, Trans. Am. Nucl. Soc. 73 (1995) 217.

[VII.13] KOPONEN, B.L., WILCOX, T.P., HAMPEL, V.E., Nuclear Criticality Experiments From 1943 to 1978, an Annotated Bibliography: Vol. 1, Main Listing, Rep. UCRL-52769, Vol. 1, Lawrence Livermore Laboratory, Livermore, CA (1979).

[VII.14] BIERMAN, S.R., Existing Experimental Criticality Data Applicable to Nuclear Fuel Transportation Systems, Rep. PNL-4118, Battelle Pacific Northwest Laboratories, Richland, WA (1983).

[VII.15] ORGANIZATION FOR ECONOMIC COOPERATION AND DEVELOPMENT, International Handbook of Evaluated Criticality Safety Benchmark Experiments, Rep. NEA/NSC/DOC(95)03, Vols I - VI, OECD, Paris (1995).

[VII.16] DURST, B.M., BIERMAN, S.R., CLAYTON, E.D., Handbook of Critical Experiments Benchmarks, PNL-2700, Battelle Pacific Northwest Laboratories, Richland, WA (1978).

[VII.17] ORGANIZATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT, Standard Problem Exercise on Criticality Codes for Spent LWR Fuel Transport Containers, CSNI Rep. N 71 (Restricted), OECD, Paris (May 1982).

[VII.18] ORGANIZATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT, Standard Problem Exercise on Criticality Codes for Large Arrays of Packages of Fissile Materials, CSNI Rep. N 78 (Restricted), OECD, Paris (August 1984).

[VII.19] JORDAN, W.C., LANDERS, N.F., PETRIE, L.M., Validation of KENO V.a - Comparison with Critical Experiments, Rep. ORNL/CSD/TM-238, Oak Ridge Natl Lab., Oak Ridge, TN (1994).

[VII.20] The 1991 International Conference on Nuclear Criticality Safety (ICNC'91) (Proc. Conf. Oxford, 1991), 3 Vols, Oxford, UK (1991).

[VII.21] The 1995 International Conference on Nuclear Criticality Safety (ICNC'95) (Proc. Conf. Albuquerque, 1995), 2 Vols, Univ. of New Mexico, Albuquerque, NM (1995).

[VII.22] DYER, H.R., PARKS, C.V., ODEGAARDEN, R.H., Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, NUREG/CR-5661 (ORNL/TM-11936), US Nuclear Regulatory Commission, Washington, DC (1997).

[VII.23] BROADHEAD, B.L., DEHART, M.D., RYMAN, J.C., TANG, J.S., PARKS, C.V., Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-term Storage of LWR Spent Fuel, Rep. ORNL/TM-12742, Oak Ridge Natl Lab., Oak Ridge, TN (1995).

[VII.24] DEHART, M.D., Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages, ORNL/TM-12973, Martin Marietta Energy Systems, Inc., Oak Ridge Natl Lab., Oak Ridge, TN (1996).

[VII.25] NAITO, Y., KUROSAWA, M., KANEKO, T., Data Book of the Isotopic Composition of Spent Fuel in Light Water Reactors, Rep. JAERI-M 94-034, Japan Atomic Energy Research Institute, Tokyo (1994).

[VII.26] BIERMA, S.R., TALBERT, R.J., Benchmark Data for Validating Irradiated Fuel Compositions Used in Criticality Calculations, Rep. PNL-10045, Battelle Pacific Northwest Laboratories, Richland, WA (1994).

[VII.27] KUROSAWA, M., NAITO, Y., KANEKO, T., "Isotopic composition of spent fuels for criticality safety evaluation and isotopic composition database (SFCOMPO)", Nuclear Criticality Safety, ICNC'95 (Proc. 5th Int. Conf. Albuquerque, 1995), Univ. of New Mexico, Albuquerque, NM (1995) 2.11 - 15.

[VII.28] HERMANN, O.W., BOWMAN, S.M., BRADY, M.C., PARKS, C.V., Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analyses, Rep. ORNL/TM-12667, Oak Ridge Natl Lab., Oak Ridge, TN (1995).

[VII.29] MITAKE, S., SATO, O., YOSHIZAWA, N., "An analysis of PWR fuel post irradiation examination data for the burnup credit study", Nuclear Criticality Safety, ICNC'95 (Proc. 5th Int. Conf. Albuquerque, 1995), Univ. of New Mexico, Albuquerque, NM (1995) 5.18 - 25.

[VII.30] BOWMAN, S.M., DEHART, M.D., PARKS, C.V., Validation of SCALE-4 for burnup credit applications, Nucl. Technol. 110 (1995) 53.

[VII.31] GULLIFORD, J., HANLON, D., MURPHY, M., "Experimental validation of calculational methods and data for burnup credit", Nuclear Criticality Safety, ICNC'95 (Proc. 5th Int. Conf. Albuquerque, 1995), Univ. of New Mexico, Albuquerque, NM (1995).

[VII.32] SANTAMARINA, A., et al., "Experimental validation of burnup credit calculations by reactivity worth measurements in the MINERVE Reactor", ibid., pp. 1b.19 - 25.

[VII.34] TAKANO, M., OKUNO, H., OECD/NEA Burnup Credit Criticality Benchmark, Result of Phase IIA, NEA/NSC/DOC(96)01, Japan Atomic Energy Research Institute, Tokyo (1996).

[VII.35] TAKANO, M., OECD/NEA Burnup Credit Criticality Benchmark, Result of Phase-IA, Rep. NEA/NSC/DOC(93)22, Japan Atomic Energy Research Institute, Tokyo (1994).

[VII.36] DEHART, M.D., BRADY, M.C., PARKS, C.V., OECD/NEA Burnup Credit Calculational Criticality Benchmark - Phase IB Results, Rep. NEA/NSC/DOC(96)-06 (ORNL-6901), Oak Ridge National Laboratory, Oak Ridge, TN (1996).

[VII.37] DEHART, M.D., PARKS, C.V., "Issues Related to Criticality Safety Analysis for Burnup Credit Applications", Nuclear Criticality Safety, ICNC'95 (Proc. 5th Int. Conf., Albuquerque, 1995), Univ. of New Mexico, Albuquerque, NM (1995) 1b.26 - 36.

[VII.38] BOWDEN, R.L., THORNE, P.R., STRAFFORD, P.I., "The methodology adopted by British Nuclear Fuels plc in claiming credit for reactor fuel burnup in criticality safety assessments", ibid., pp. 1b.3 - 10.

[VII.39] ZACHAR, M., PRETESACQUE, P., "Burnup credit in spent fuel transport to COGEMA La Hague reprocessing plant", Int. J. Radioact. Mater. Trans. 5 2 - 4 (1994) 273 - 278.

[VII.40] EWING, R.I., "Burnup verification measurements at US nuclear utilities using the Fork system", Nuclear Criticality Safety, ICNC'95 (Proc. 5th Int. Conf. Albuquerque, 1995), Univ. of New Mexico, Albuquerque, NM (1995) 11.64 - 70.

[VII.41] EWING, R.I., "Application of a Burnup Verification Meter to Actinide-only Burnup Credit for Spent PWR Fuel", Packaging and Transportation of Radioactive Materials, PATRAM 95 (Proc. 11th Int. Conf. Las Vegas, 1995), USDOE, Washington, DC (1995).