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Full text (ru) Constant support of physical calculations subsystem of in-core monitoring system “Voyage”
V. V. Galchenko1,2,*, A. A. Mishin2, I. I. Shlapak1
1 Private Joint Stock Company “Severodonetsk Research and Production Association “Impulse”, Severodonetsk, Ukraine
2 Limited Liability Company “Nuclear Power Plant Operational Support Institute”, Kyiv, Ukraine
*Corresponding author. E-mail address:
v.galchenko@npp-osi.kiev.ua
Abstract: In this study a brief description of the polynomial interpolation of few-group constants on sparse grids for VVER-1000 reactor is adduced. The calculations about various burnup instances were made for the method. Besides, comparative analysis of the irregularity factor of kv è kq calculation was made with the help of the preparation of constants by using this method while arranging by different software products.
Keywords: in-core monitoring system, HELIOS, VVER-1000, cross-section, power distribution, computer codes.
References:1. S.V. Shirokov. Physics of Nuclear Reactors. 2-nd edition (Kyiv, 1998) 228 p. (Rus)
2. I. Bilodid et al. Assessment of Spectral History Influence on PWR and WWER core. Kerntechnik 77(4) (2012) 278. http://dx.doi.org/10.3139/124.110254
3. V.V. Galchenko. Data preparation comparison analysis using difference computer codes. Part 2. Nuclear and Radiation Technologies 7(3-4) (2007) 29. (Rus)
4. V.D. Sidorenco et al. Spectral Code TVS-M for Calculation of Cells, Supercells and Fuel Assemblies VVER-type Reactors. 5-th Symposium of the AER. Dobotoko, Hungary, Oct. 15 - 20, 1995.
5. V.A. Bragin et al. VVER-1000 NPP’s In-core Monitoring System. Ed. G.L. Levin (Ìoskva: Energoatomizdat, 1987) 128 p. (Rus)
6. J. Watson et al. Cross-Section Generation Methodology for Three-Dimensional Transient Reactor Simulation (TANSAO77, 1997) 175 ð.
7. E.A. Zholkevich. Neutron-physics dependences approximation for VVER grid dependence from core parameters. OKA Soft. Preprint IAE-3558/5 (Ìoskva, 1982) 69 p. (Rus)
8. D.M. Petrunin, E.D. Beliayeva, E.L. Kireeva. BIPR-5 – computer code for three-dimensional power distribution and burnup calculation in one-group approach for VVER reactor type. Preprint IAE-2518 (Ìoskva, 1975) 33 p. (Rus)
9. A.A. Marakazov. VVER reactor type fuel assemblies power calculation method in two-group diffusion approach (Moskva, IAE, 1977) 30 p. (Rus)
10. A.B. Bakushinskiy, V.K. Vlasov. Mathematics Elements and Numerical Methods. Ed. E.S. Berezin (Ìoskva: Prosveshchenie, 1968) 336 p. (Rus)
11. V.V. Galchenko, O.V. Nedelin. Comparative analysis of few-group constants preparation with the use of different computer codes. Part 1. Nuclear and Radiation Safety 6(3) (2003) 61. (Rus)
12. O.V. Samoylichenko, V.M. Mokiychuk. Analytical methods validation, like part of tested results quality provided. Elektrotekhnichni ta Kompyuterni Systemy 6(82) (2012) 228 p. (Ukr) http://etks.opu.ua/?fetch=articles&with=info&id=209
13. J.R. Askew, F.J. Fayers, P.B. Kemshell. A general description of the lattice code WIMS. Journal of British Nuclear Energy Society 5(1) (1966) 564. https://senior.app.box.com/v/BNES-VOL5-4
14. J.J. Casal et al. HELIOS: Geometric Capabilities of a New Fuel-Assembly Program. Proc. Int. Top. Mtg. Adv. Math. Comp. Reac. Phys., Pittsburg, PA, USA, 1992. Vol. II, Sect. 10.2.1, 1-13.
15. V.V. Galchenko, A.A. Mishyn. Comparative analysis of reactor cycle neutron characteristics using different WIMSD5B nuclear data libraries. Nuclear and Radiation Safety 3(67) (2015) 8. (Ukr) http://sstc.com.ua/documents/journal/2015/3/text/2_3_2015_text.pdf
16. I. Ovdiienko et al. Development of cross-section library for DYN3D code. Nuclear and Radiation Safety 4(64) (2014) 22. http://www.sstc.com.ua/documents/journal/2014/4/4_4_2014_text.pdf
17. A VVER-1000 LEU and MOX Assembly Computational Benchmark. Specification and results. Nuclear Science NEA/NSC/DOC(2002)10. 156 p. https://www.oecd-nea.org/science/docs/2002/nsc-doc2002-10.pdf