Problems of Reliability Indicators Increase of Critical Heat Flux Calculations in the Water-Cooled Nuclear Reactors Based on the Computer Thermal-Hydraulic Codes
ARTICLE PDF

Keywords

thermal-hydraulic computer codes, critical heat flux, heat transfer crisis

How to Cite

Sharaevsky, G. (2018). Problems of Reliability Indicators Increase of Critical Heat Flux Calculations in the Water-Cooled Nuclear Reactors Based on the Computer Thermal-Hydraulic Codes. Nuclear and Radiation Safety, (3(79), 16-22. https://doi.org/10.32918/nrs.2018.3(79).03

Abstract

The analysis of the current state of research and developments in the field of creation of thermal-hydraulic computer codes has been performed. The experience of creation of foreign versions of best-estimate codes was analyzed. Considerable attention is paid to the issue of critical heat flux calculation of nuclear reactors channels. It is demonstrated that now the efficiency of application of modern computer codes for estimating of the heat transfer crisis in the water-cooled nuclear reactors requires further improvement. Calculation methods for accuracy increase of predicting this thermal-hydraulic phenomenon in reactor channels are considered. The well-known methods of critical thermal flux in nuclear reactors channels have been analyzed. Peculiarities of determination of the heat transfer crisis in the forced of the vapor-water steam motion have been reviewed. Adequacy of software computer codes designed to calculate the main safety parameters of water-cooled nuclear reactors was analyzed. The idea of the physical mechanism of the heat transfer crisis under forced motion of a two-phase flow in heated channels was considered. Particular attention has been paid to analysis of experimental and calculated data on conditions of initiation of a heat transfer crisis in fuel assemblies rods.

https://doi.org/10.32918/nrs.2018.3(79).03
ARTICLE PDF

References

1. Nosovsky, А. V.; Sharaevsky, I. G.; Fialko, N. М.; Zimin, L. B.; Sharaevsky, G. I. (2017), “Thermal Physics of the Nuclear Power Plants Lifetime” [Teplofizika resursa yadernykh energoustanovok], Institute for Safety Problems of NPP NAS of Ukraine”, 624 p. (Rus)

2. Bobkov, V. P. (2015), “Critical Heat Flux in a Boiling Water Channels. Current State, Common Factors, Unresolved Problems and Ways of their Solution” [Kriticheskiy teplovoy potok pri kipenii vody v kanalakh. Sovremennoye sostoyaniye, kharakternyye zakonomernosti, nereshennyye problemy i puti ikh resheniya], Теplоenergetika, Iss. 2, pp. 10—18. (Rus)

3. Bobkov, V. P.; Sudnitsyn, О. А.; Sudnitsyna, М. О. (1998). “Numerical and Analytical Description of Critical Heat Flows in Channels” [Chislennoye i analiticheskoye opisaniye kriticheskikh teplovykh potokov v kanalakh], Nuclear Energy0, Iss. 84. Vol. 2, pp. 114—123. (Rus)

4. Shkarupa, А. М., Kadenko, I. N., (2006), “Application of RELAP5-3D Code to Support Safety Analysis Ukrainian NPP Power Units” [Primeneniye koda RELAP5-3D v podderzhku analiza bezopasnosti energoblokov AES Ukrainy], Nuclear Physics and Energy, Iss. 2 (18), pp. 75—81. (Rus)

5. Sharaevsky, I. G. (2010), “Recognition of transient Thermal-Hydraulic Processes in Water-Cooled Nuclear Power Reactors” [Rozpiznavannya peredavariynykh teplohidravlichnykh protsesiv u vodookholodzhuvanykh yadernykh enerhetychnykh reaktorakh], Doctor Thesis, Kyiv, IPB AES NAS of Ukraine, 48 p. (Ukr)

6. Bobkov, V. P.; Smogalev, I. P. (2001), “On Accuracy of Description by by Different Codes of Various Critical Heat Fluxes in Beam Bundles” [O tochnosti opisaniya razlichnymi kodami kriticheskikh teplovykh potokov v puchkakh sterzhney], Теploenergetika, Iss. 3, pp. 21—28. (Rus)

7. Kirillov, P. L.; Yuriev, Yu. S.; Bobkov, V. P. (1990). “Thermohydraulic Calculations Handbook (nuclear reactors, heat exchangers, steam generators)” [Spravochnik po teplogidravlicheskim raschetam (yadernyye reaktory, teploobmenniki, parogeneratory)], 2nd revision, updated, Moscow, Energoatomizdat. (Rus)

8. Kliuchnykov, А. А.; Sharaevsky, I. G.; Fialko, N. M.; Zimin, L. B.; Sharaevsky, G. I. (2015). “Thermal Physics of Cores Reliability” [Teplofizika nadezhnosti aktivnykh zon], Institute for Safety Problems of NPP NAS of Ukraine, 772 p. (Rus)

9. Vorobyov, Yu. Yu.; Zhabin, О. I.; Tereshchenko, I. А. (2014). “Peculiarities of Modeling of MCP Jamming and Accounting of RELAP5/MOD3.2 Calculation Code for Analysis of Beyond Design-Basis Accidents for WWER-1000” [Osobennosti modelirovaniya zaklinivaniya GTsN i uchet zakrizisnogo teploobmena pri pomoshchi raschetnogo koda RELAP5/MOD3.2 dlya analiza proyektnykh avariy dlya reaktorov tipa VVER-1000], Nuclear and Radiation Safety, Iss. 4, pp. 17—21. (Rus)