Abstract
Some experience related to the preparation and validation of neutronic models based on the SAPFIR code package is presented. Development and verification of neutronic parameters for two types of reactors with thermal and intermediate neutron spectra are described.
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References
Tabin I, Buchov V, Sergeev V. Ivanov A et al (1985) Software package SAPFIR for reactor cells calculcation:: VANT, series Nuclear Reactors Physics and Engineering, 4, pp. 68–71.
Karpov, A, Tabin, V. (1995) Many group neutron data preparation system for SAPFIR package with NJOY-B30 code system. Proceedings of Neutronic-95 seminar, Obninsk, Russia.
Tabin V, Judkevich I, (1985) generalized subgroup approach to resonance absorption calculation: Atomic energy, v. 59, iss. 2, p. 96.
Gomin E., Maiorov L. (1982) Code TERMAC for group neutron cross-sections in thermalization region VANT, series Nuclear Reactor Physics and Engineering, 5 (27), n. 70.
Pisarev P. (1992) Modules OTRAWA and SVP for burnup calculations in BMVC and SAPFIR codes, Third conference proceeding “Nuclear Technology Tomorrow”, Leningrad.
Gomin E., Maiorov L. (1982) About FCP calculation in complex geometry systems, VANT, series Nuclear Reactors Physics and Engineering 8 (21), p. 62–69.
Alexeev N., Gurevich I. (1993) Geometry module SCG-5. Preprint IAE-5616/4.
Ivanov A. (1984) Bank of neutron constants of Institute of Kurchatov, Institute of Atomic Energy: VANT, series Nuclear Data 6 (43), p. 55–56.
Judkevich I. (1984) Bank of neutron constants of Institute of Kurchatov Institute of Atomic Energy: VANT, series Nuclear data, 5 (59), p. 3.
Artemov V., Ivanov A, Piscarev A, Obuchov V., Shemaev Yu. (1996) The set of tests and V&V experience calculation core code system SAPFIR_VVR95-RC on water-water propulsion reactors facilities. Proceedings of Neutronic-96 seminar, Obninsk, Russia.
M.L. Williams, R.Q. Wright et al. (1985) Analysis of Thermal Reactor Benchmarks with Design Codes Based on ENDF/B-V Data. Nuclear Technology, vol. 71, pp. 386–401
Mosteller R.D. etc. (1989) Benchmarking CELL-2 Using a Monte Carlo Method, NSAC-136.
Mosteller R.D. etc. (1991) Benchmark calculations for the Doppler Coefficient of Reactivity, Nuclear Science and Engineering 8, p. 437.
Y. Ishiguro, H. Akie, H. Takano (1988) Preliminary Report of HCLWR Cell Burnup Benchmark Calculation, NEACRP-A-849
Stepanov A., Makarova A. et all (1983) Burnup and isotope composition determination VVER-440 spent fuel, Atomic energy, vol. 55, is. 3
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© 1999 Springer Science+Business Media Dordrecht
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Artemov, V. et al. (1999). Development of Neutronic Models for two Types of Reactors Based on the Sapfir Package of Universal Algorithms. In: Parish, T.A., Khromov, V.V., Carron, I. (eds) Safety Issues Associated with Plutonium Involvement in the Nuclear Fuel Cycle. NATO Science Series, vol 23. Springer, Dordrecht. https://doi.org/10.1007/978-94-011-4591-6_19
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DOI: https://doi.org/10.1007/978-94-011-4591-6_19
Publisher Name: Springer, Dordrecht
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