Abstract
A method is presented for determining the burnup of spent nuclear fuel during reloading. The method is based on an analysis of the results of γ spectrometric measurements performed at the Zaporozh'e nuclear power plant. This method differs from existing methods in that the initial enrichment of the nuclear fuel and the holding time of the nuclear fuel after irradiation are determined.
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REFERENCES
PNAÉ G-14-029-91. Safety Rules for Storage and Shipment of Nuclear Fuel at Nuclear Power Plants, TSNIIatominform, Moscow (1992).
O. V. Maslov and S. G. Oleinik, “Apparatus and methods for monitoring highly radioactive materials and fuel in technology for handling spent nuclear fuel,” in: International Conference of the Ukrainian Nuclear Society, Kiev (2000), pp. 42–44.
D. Riley, N. Ensslin, and H. Smith, Passive Nondestructive Analysis of Nuclear Materials [Russian translation], ZAO Izdatel'stvo Binom, Moscow (2000).
S. Hsue, T. Crane, W. Talbert, Jr, and J. Lee, “Nondestructive assay methods for irradiated nuclear fuels,” Report LA-6923-MS, Los Alamos National Laboratory (1978).
I. Ronald, D. Bronowski, G. Boster, and R. Siebelist, “Measurements on spent-fuel assemblies at Arkansas Nuclear one using the fork system,” Sandia National Laboratory Report SAND-96-1364 (1997).
Yu. N. Pytkin, S. A. Andrushechko, B. Yu. Vasil'ev, and S. N. Goloshchapov, “Adoption of an apparatus at the Kola nuclear power plant for measuring the degree of burnup of spent fuel assemblies,” in: International Conference on Taking into Account, Monitoring, and Physical Shielding of Nuclear Materials, Obninsk (1997), pp. 637–645.
D. Haggaard and J. Tanner, “Determination of Curie content and 134/137cesium ratios by γspectroscopy of high burnup plutonium- aluminum fuel assemblies,” Pacific Northwest National Laboratory Report PNNL-11609 (1997).
A. Tiitta, A. Dvoeglazov, S. Levlev, and M. Tarvainen, “Specification of an industrial prototype,” International Report on Task FIN A 1073 of the Finnish Support Program to IAEA Safeguards, STUK-YTO-TR 161, Helsinki (2000).
O. V. Maslov, M. V. Maksimov, and S. G. Oleinik, “Substantiation of radiation methods for monitoring the state of nuclear fuel in real time when performing reloading,” Trudy Odes. Politekhn. Univer., No. 3(12), 50–55 (2000).
O. V. Maslov and S. G. Oleinik, “Automated system for monitoring the distribution of fission products in VVÉR-1000 fuel assemblies while performing nuclear fuel reloading,” in: 2nd International Conference on Taking into Account, Monitoring, and Physical Shielding of Nuclear Materials, Obninsk (2000), pp. 370–388.
O. N. Galchenkov, O. V. Maslov, and S. G. Oleinik, “Comparison of two methods for constructing spectra in a digital gamma spectrometer,” Yad. Radiats. Bezopas., 3, No. 3, 61–63 (2000).
I. V. Maslov, S. G. Oleinik, L. L. Kal'nev, and S. A. Savel'ev, “Determination of the degree of burnup of nuclear fuel in real time while performing reloading,” Avtomat., Avtomatizats., Élektrotekhn. Komplek. Sist., No. 1(6), 141–148 (2000).
P. Jansson, A. Hekansson, and A. Backlin, “Measurements of spent PWR fuel and determination of residual power,” Report ISV-7/97, Department of Radiation Sciences, Uppsala University (1997).
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Oleinik, S.G., Maksimov, M.V. & Maslov, O.V. Determination of the Burnup of Spent Nuclear Fuel during Reloading. Atomic Energy 92, 296–300 (2002). https://doi.org/10.1023/A:1016593608146
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DOI: https://doi.org/10.1023/A:1016593608146