PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

BROND-3.1

ISSUES

2019, Issue 3

IMPACT ASSESSMENT OF COOLANT DENSITY VARIATION ON THE ACCURACY OF VVER ENERGY RELEASE CALCULATION

DOI: 10.55176/2414-1038-2019-3-80-88

Authors & Affiliations

Artemov V.G.1, Kuznetsov A.N.1, Kurakin K.Yu.2, Tikhomirov A.V.2
1 Alexandrov Research Institute of Technoloqy, Sosnovy Bor, Russia
2 Experimental and Design Organization "GIDROPRESS", Podolsk, Russia

Artemov V.G. – Head of laboratory, Cand. Sci. (Techn.), Alexandrov Research In-stitute of Technoloqy.
Kuznetsov A.N. – Head of group, Senior Researcher, Alexandrov Research In-stitute of Technoloqy. Contacts: 72, Koporskoe shosse, Sosnovy Bor, Leningrad region, Russia, 188540. Tel.: +7(81369) 6-08-83; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kurakin K.Yu. – Head of Department, Experimental and Design Organiza-tion "GIDROPRESS".
Tikhomirov A.V. – Leading design engineer, Experimental and Design Organiza-tion "GIDROPRESS".

Abstract

This paper presents the verification results of SAPFIR_95&RC_micro program that is intended for fine-grid three-dimensional pin-by-pin calculation of power in VVER reactor core at change of coolant density. In this paper, fine-grid three-dimensional pin-by-pin power calculation is typically seen as calculation where pin-by-pin power is computed on the finite-difference grid that matches the fuel rod spac-ing in fuel assembly. MCNP-based calculation was used as a benchmark; this calculation was prepared for one of the first fuel loadings of the NPP-2006 reactor. A series of two-dimensional calculations has been performed: in each test the same coolant density over the reactor core (variation of water density from 0.3 to 0.8 g/cm3) is set, coolant temperature is considered as invariable and is 315 °C. Three-dimensional calculation has been performed: different density (range of 0.46—0.73 g/cm3) in ten layers along the core axis is set, coolant temperature is varying from 299 to 348 °C. The influence of number of energy groups on the accuracy of power calculation for fuel rods and gadolinium fuel rods is analyzed. Two-, six- and twelve-group diffusion approximation are calculated. The calculation model is prepared using SAPFIR_95.1 cell calculation program and SAPFIR_95&RC_micro pin-by-pin power calculation program.

Keywords
 reactor calculation, pin-by-pin energy release, “fine-grid” computation

Article Text (PDF, in Russian)

References

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2019, issue 3, 3:7