KnE Engineering

ISSN: 2518-6841

The latest conference proceedings on all fields of engineering.

Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility

Published date: Feb 21 2018

Journal Title: KnE Engineering

Issue title: XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"

Pages: 279-290

DOI: 10.18502/keg.v3i3.1627

Authors:

V.I. Slobodchuk

E.A. Avramova

E.M. Shchennikova

D.A. Shal'kov

Abstract:

The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolant using a light water test facility. A large nuclear power reactor (like the BN-1200 project) was selected as a reactor installation to be modeled. To validate the model, the similarity theory and the “black box” method were used. The paper uses the experience of a number of researchers in this field, in particular, the accepted assumptions which do not result in serious loss in modeling accuracy. The governing criteria of similarity were estimated based on the fundamental differential equations of convective heat transfer, so were the conditions under which it is possible to model sodium coolant by using  light water with adequate accuracy. The paper presents the scales of the parameters used for the model - reactor comparison. Dependence curves of certain scales with regard to others are constructed, and the possibility of achieving similarity of certain parameters in modeling was estimated. Recommendations are provided on designing a water test model of the BN reactor and on carrying out experiments using this test model.

References:

[1] Ashirmetov M. R., Rezultaty realisazii novoi technologicheskoi platformy yadernoi energetiki//, http://www.atomic-energy.ru/events/55252, 4.04.2015 г. (in Russian)


[2] Ashirmetov M. R., Ershov G.A. . Osnovnye proektnye resheniya dlya energobloka BN-1200,// http://www.proatom.ru/, 25.01.2013 г. (in Russian)


[3] Mitenkov F.M. Perspectivy rasvitiya bystrykh reaktorov-razmnozgitelei, http://www.proatom.ru/, 22.01.2013 г. (in Russian)


[4] Eguchi Y., Takeda H., Koga T., Tanaka N., Yamamoto K. Quantitative Prediction of Natural Circulation using a Similarity Law and Scaled Water Test Model // Nuclear Engineering and Design 178 (1997), 295–307.


[5] Eguchi Y., Yamamoto K., Fundo T., Koga T., Takeda H., Sasaki K., Kajiwara H., Toda M., Maekawa I. Experimental and Computational Study on Prediction of Natural Circulation in Top-entry Loop-type FBR // Presented for IAEA Specialist Meeting on Evaluation of Decay Heat Removal by Natural Convection, held at Oarai Engineering Center. 22-25 Feb. 1993.


[6] Adamov E.O. Proyekt “Proryv”: sozdanie yadernykh energotechnologiy novogo pokoleniya,// http://docplayer.ru/35356756, 29.11.2012 г. (in Russian)


[7] Guchman A.A. Vvedeviye v teoriyu podobiya. Uchebnoe posobie dlya VTUSov, isd 2-e, dop. I pererabotannoe, //M. Vysshsaya shkola, 1973, 296 p. (in Russian)


[8] Isaev S.I., Kozgin I.A., Kofanov V.I. i dr. Teoriya teplomassoobmena, Uchebnik dlya VUSov, //M.: Vysshaya Shkola, 1975, 495 p. (in Russian)


[9] Kirillov P.L., Bogoslovskaya G.P., Teplomassoobmen v yadernykh enegreticheskikh ustanovkakh,// M. Energoatomizdat, 2000, 456 p. (in Russian)


[10] Kirillov P.L., Yuriev Yu.S., Bobkov V.P. Spravochnik po teplogidravlicheskim raschetam (yadernye reaktory, teploobmenniki, parogeneratory), 2-e izd. Pererab. i dop., //M,: Energoatomizdat, 1990, 360 p. (in Russian)


[11] Kirpichev M.V., Teoriya podobiya, //M.: Izdatel’stvo Akademiy Nauk SSSR, 1953. (in Russian)


[12] Mitenkov F.M. Reaktory na bystrykh neitronakh I ikh rol’ v stanovleniy bol’shoy atomnoy energetiki.// Nauka i zgisn’, 3, (2005).(in Russian)


[13] Petukhov B.S., Genin L.G., Kovalev S.A. Teploobmen v yadernykh energeticheskikh ustanovkakh. Pod red. Petukhova B.S. Uchebnoe posobie dlya VUSov. //M.: Atomizdat, 1974, 408p.(in Russian)


[14] Ushakov P.A., Sorokin A.P. Problemy modelirovaniya na vode avariynogo otvoda ostatochnogo teplovydeleniya estestvennoi konvekziey v kamerakh bystrykh reactorov. //FEI, Obninsk, 1993 (in Russian).


[15] International Atomic Energy Agency, IWGFR/88. Specialist’s Meeting on «Evaluation of Decay Heat Removal by Natural Convection». 22-23 Feb. 1993. Oarai Eng. Center, PNC, JAPAN.


[16] Ieda Y., Kamide H., Ohshima H., Sugawara S., Ninokata H. Strategy of Experimental Studies in PNC on Natural Convection Decay Heat Removal // Presented for IAEA Specialist Meeting on Evaluation of Decay Heat Removal by Natural Convection, held at Oarai Engineering Center. 22-25 Feb. 1993., pp.37-50.


[17] Suh K.Y., Todres N.E., Rohsenow W.M. Mixed Convective Low Flow Pressure Drop in Vertical Rod Assemblies: II-Experimental Validation. //Trans. of the ASME, November 1989, vol.111, pp. 966-973.


[18] Takeda H., Koga T. Study on Similarity Rule for Natural Circulation Water Test of LMFBR // Presented for IAEA Specialist Meeting on Evaluation of Decay Heat Removal by Natural Convection, held at Oarai Engineering Center. 22-25 Feb. 1993., pp. 58-66.


[19] Xu Mi. The Status of Fast Reactor Technology in China // Proc. of the 27th Meeting of the IWGFR «Status of Liquid Metal Fast Reactor Development», Vienna, 17-19 May 1994. IAEA-TECDOC-791, 1995, pp. 120-133.


[20] Kamide H., Ieda Y., Toga S., Isozaki T., Sugawara S. Multi-bundle Sodium Experiments for Thermohydraulics in Core Subassemblies during Natural Circulation Decay Heat Removal Operation // Presented for IAEA Specialist Meeting on Evaluation of Decay Heat Removal by Natural Convection, held at Oarai Engineering Center. 22-25 Feb. 1993, pp. 127-134.

Download
HTML
Cite
Share
statistics

493 Abstract Views

173 PDF Downloads