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В.Г. Крапивцев, В.А. Гуров
10
Experimental study of hydraulic characteristics
of honeycomb type spacer grids
© V.G. Krapivtsev, V.A. Gurov
Bauman Moscow State Technical University, Moscow, 105005, Russia
This article presents experimental studies of hydraulic characteristics of honeycomb type
spacer grids, applied in fuel assemblies of PWR reactors. We examine the fragments of
the gratings used, work area and aerodynamic stand. According to the procedures de-
scribed above, we give results of measurements and determine the hydraulic resistance of
the studied types of spacer grids. We conduct a comparative analysis of hydraulic char-
acteristics of the spacer grids with cells of various types.
Keywords
: PWR, fuel assembly, fuel rod, spacer grid, heat exchange intensification, stat-
ic pressure coefficient, hydraulic resistance.
REFERENCES
[1]
Denisov V.P., Dragunov Yu.G.
Reaktornye ustanovki VVER dlya atomnykh
elektrostantsiy
[Pressurized-water reactor systems for nuclear power plants].
Moscow, IzdAT Publ., 2002, 480 p.
[2]
Adamov E.O., ed.
Mashinostroenie. Entsiklopediya. Mashinostroenie yadernoy
tekhniki
[Mechanical Engineering. Encyclopaedia. Engineering in nuclear
technologies]. Moscow, Mashinostroenie Publ., 2005, vol. IV-25, book 1, 960 p.
[3]
Strategiya razvitiya atomnoy energetiki Rossii v pervoy polovine XXI
[Strategy
for the nuclear energy development in Russia in the first half of the XIX
century]. Approved by the RF Government. Proceed. no.17, 25 May 2000.
[4]
Perepelitsa N.I.
Atomnaya tekhnika za rubezhom — Atomic Energy Technology
Abroad
, 2006, no. 1, pp. 3–39.
[5]
Perepelitsa N.I.
Atomnaya tekhnika za rubezhom — Atomic Energy Technology
Abroad
, 2006, no. 2, pp. 3–9.
[6]
Markov P.V., Solonin V.I.
Vestnik MGTU. Ser. Mashinostroenie
—
Herald of
Bauman Moscow State Technical University. Ser. Mechanical Engineering
,
2011, no. 3, pp. 17–29.
[7]
Krapivtsev V.G., Solonin V.I., Tsirin S.I.
Izvestiya vysshikh uchebnykh
zavedeniy. Mashinostroenie — Proceedings of the higher educational
institutions. Mechanical Engineering
, 2011, no. 4, pp. 7–12.
[8]
Markov P.V.
Yadernaya energetika — Proceedings of Universities. Nuclear
power
, 2012, no. 1, pp. 117–125.
[9]
Getya S.I., Krapivtsev V.G., Markov P.V., Solonin V.I., Tsirin S.I.
Atomnaya
energiya — Atomic Energy
, 2013, vol. 114, no. 1, pp. 55–57
[10]
Kirillov P.L., Yurev Iu.S., Bobkov V.P.
Spravochnik po teplogidravlicheskim
raschetam (Yadernye reaktory, teploobmenniki, parogeneratory)
[Handbook
of thermal-hydraulic calculations (Nuclear reactors, heat exchangers, steam
generators)]. Moscow, Energoatomizdat Publ., 1984, 296 p.
Krapivtsev V.G
. (b. 1949) graduated from Bauman Moscow State Technical University
in 1972. Cand. Sci. (Eng.), Assoc. Professor of “Nuclear reactors and facilities” Depart-
ment at Bauman Moscow State Technical University. Scientific interests include compu-
tational and experimental studies of hydrodynamic processes in reactors PWR, develop-
ment in improving the design of nuclear fuel in pressurized-water reactor, high-power
channel-type reactor. е-mail:
hykloh@mail.ru