EDN: AMRSDC
Authors & Affiliations
Dmitriev D.V., Gonchar N.I., Jilkin A.S.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Dmitriev D.V. – Research Engineer of the 2 category. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-54-21; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Gonchar N.I. – Leading Researcher, Cand. Sci. (Tech.).
Jilkin A.S. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Abstract
During the operation of reactor plants,
gaseous fission products accumulate in the internal gas volumes of fuel rods of
the container type. In this regard, the internal pressure increases under the
fuel element shell, which can lead to the appearance of a defect. The greatest
danger is damage to the fuel element shells, which reach high levels of fuel
burnout when the gas pressure inside the fuel element becomes maximum.
To assess the
pressure under the fuel element shell, it is necessary to correctly (from a
physical point of view) describe the accumulation and release of gaseous
fission products from the fuel, as well as to model their distribution in the
internal volumes of the fuel element. Solving this problem in Russia and the
world, engineering programs have been developed.
The paper presents a mathematical model of the release of stable gaseous fission products
from fuel and their distribution in a container-type fuel element with uranium
oxide fuel, and also compares the calculated data obtained using a mathematical
model, according to the Alpha-M program for fuel elements of fuel assemblies of
the BN-600 reactor.
Keywords
reactor plants, mathematical model, fuel
output, gaseous fission products, pressure under the fuel element shell, fuel
element of a BN type reactor, Alpha-M program, calculated estimates, comparison
of calculated estimates
Article Text (PDF, in Russian)
References
1. Federal'nyye normy i pravila v oblasti
ispol'zovaniya atomnoy energii «Obshchiye polozheniya obespecheniya
bezopasnosti atomnykh stantsiy» (NP-001-15)
[Federal Norms and Rules in the Field of atomic energy Use “General provisions
for ensuring the safety of nuclear power plants” (NP-001-15)]. Moscow, 2016.
2. Svidetel'stvo o registratsii programmy
Al'fa-M-S15 [Certificate of
registration of the Alfa-M-S15 program]. No. 2019612945 dated December 28, 2018.
3. Zhilkin A.S., Osipov S.L., Salyaev A.V., Semenov
V.N., Filippov M.F., Tsaun S.V. Chislennoye modelirovaniye povedeniya produktov
korrozii i gazoobraznykh produktov deleniya v kode SOKRAT-BN [Numerical modeling
of the behavior of corrosion products and gaseous fission products in the
SOKRAT-BN code]. Izvestiya Akademii nauk. Energetika – Proceedings of the Academy of Sciences. Energy,
2014, no. 3, pp. 97–105.
4. Rausch W.N., Panisko F.E. ANS54: A Computer
Subroutine for Predicting Fission Gas Release. Pacific Northwest
Laboratory, 1980.
5. Warner H.R., Nichols F.A. A Statistical Fuel
Swelling and Fission Gas Release Model. Nucl. Appl. Technol., 1970,
vol. 9, issue 2,
p. 148–166. DOI: 10.13182/NT70-A28805.
6. Kolobashkin V.M., Rubtsov P.M., Ruzhansky P.A., Sidorenko V.D. Radiatsionnyye kharakteristiki obluchonnogo
yadernogo topdiva. Spravochnik [Radiation characteristics of irradiated nuclear fuel. Handbook].
Moscow, Energoatomizdat Publ., 1983. 382 p.
7. Konyashov V.V., Shkokov E.I. Vykhod
radioaktivnykh PD iz defektnykh tvelov s oksidnym toplivom. Obzor po otech. i
zarubezh. istochnikam 1964–1986 [The output of radioactive PD from
defective fuel rods with oxide fuel. Review]. Moscow, Tsniiatominform Publ.,
1987. 57 p.
8.
Lastman B. Radiatsionnyye
yavleniya v dvuokisi urana [Radiation phenomena in uranium dioxide]. Moscow, Atomizdat Publ.,
1964. 288 p.
9. Kazansky Yu.A., Troyanov M.F., Matveev V.I., Evseev A.Ya., Zvonarev A.V., Kiryushin A.I.,
Vasiliev B.A., Belov S.P., Matveenko I.P., Kulabukhov Yu.S., Cherny V.A.,
Bakov A.T., Dvukhsherstnov V.G., Ivanov A.P., Tyutyunnikov P.L., Pshakin
G.M. Issledovaniye fizicheskikh kharakteristik pri puske reaktora BN-600. Iz
istorii rabot FEI po sozdaniyu bystrykh reaktorov [Investigation of physical
characteristics during the start-up of the BN-600 reactor. From the history of
FEI's work on the creation of fast reactors]. Sbornik izbrannykh nauchnykh
rabot. K 80-letiyu dnya rozhdeniya M.F. Troyanova [Proc. of Selected
Scientific Papers. To the 80th Anniversary of M.F. Troyanov's birthday].
Obninsk, IPPE Publ., 2011.
10. Oshkanov N.N., Govorov P.P. Zhidkometallicheskiy reaktor BN-600 –
osnovnyye osobennosti i opyt ekspluatatsii [BN-600 Liquid Metal Reactor – Main
Features and Operating Experience]. Izvestiya vuzov. Yadernaya energetika,
2009, no. 2, pp. 7–20.
11. Usloviya raboty tvelov reaktorov na bystrykh neytronakh i
pred"yavlyayemyye k nim trebovaniya. Energetika. TES i AES [Operating conditions of fuel rods of fast
neutron reactors and requirements for them. Energy. Thermal power plants and
nuclear power plants]. Available at: https://tesiaes.ru/?p=13832
(accessed 22.09.2021).
UDC 621.039.584
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 2, 1:4
