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DEVELOPMENT OF A MODEL FA FOR THE STUDY OF EMERGENCY SITUATION WITH AN IMMEDIATE BLOCKING OF THE COOLANT FLOW IN FAST REACTOR

https://doi.org/10.52676/1729-7885-2018-3-93-98

Abstract

Possibilities of experimental study of the model fuel assembly (FA) destruction of ASTRID reactor in a severe accident were studied in this paper. Experiments with model FA can be carried out in a research impulse graphite reactor (IGR) [1] in the framework of joint program between RSE NNC RK and CEA, called SAIGA (SAIGA – Severe Accident InPile experiments for Generation IV reactor and Astrid project) [2].
ASTRID reactor core consists of an inner zone with heterogeneous FA in height, in which the principle of separation of high enrichment fuel into two zones (upper and lower) is applied by fuel layer with a low uranium-235 content, intended for the reproduction of fission substances, and an external zone with homogeneous FA [3]. The study considers two versions of the model FA for reactor tests, which differ in the geometry and composition of the fuel elements installed in them. Test modes of model FA are determined and complex calculations on their justification is conducted.

About the Authors

V. A. Vityuk
RSE “National Nuclear Center of the Republic of Kazakhstan”
Kazakhstan
Kurchatov


A. D. Vurim
Branch “Institute of Atomic Energy” RSE NNC RK
Kazakhstan
Kurchatov


V. M. Kotov
Branch “Institute of Atomic Energy” RSE NNC RK
Kazakhstan
Kurchatov


G. A. Vityuk
Branch “Institute of Atomic Energy” RSE NNC RK
Kazakhstan
Kurchatov


F. Serre
Commissariat of atomic energy and alternative energy sources (CEA)
France
Cadarache


F. Payot
Commissariat of atomic energy and alternative energy sources (CEA)
France
Cadarache


C. Suteau
Commissariat of atomic energy and alternative energy sources (CEA)
France
Cadarache


L. Trotignon
Commissariat of atomic energy and alternative energy sources (CEA)
France
Cadarache


References

1. Курчатов, И.В. Импульсный графитовый реактор ИГР / И.В. Курчатов, С.М. Фейнберг, Н.А. Доллежаль // Атомная энергия. – 1964. – Т. 17, № 6. – С. 463-474.

2. Serre, F., et al., "R&D and Experimental Programs to support the ASTRID Core Assessment in Severe Accidents Conditions". – Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP), 2016, San Francisco (CA, USA), April 17–20, 2016, Paper 16394.

3. The ASTRID technological demonstrator. 4th-Generation sodium-cooled fast reactors. –Tome 3, December, 2012., 96 pages.

4. P. SCIORA, et al., “Low void effect core design applied on 2400 MWth SFR reactor” – Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011.

5. Kotov V.М., Irkimbekov R.A., Kurpesheva A.M., Bench-Mark model of the IGR reactor. - The collection of theses of 8th International conference «Nuclear and radiation physics», Almaty, 20-23th. September, 2011., p. 37.

6. MCNP 5: A General Monte Carlo N – Particle Transport Code, Version 5, 2003.

7. ANSYS, Inc. Products Release 14.0, 2014.

8. Чиркин, В.С. Теплофизические свойства материалов ядерной техники / В.С. Чиркин; М. : Атомиздат, 1968. – 121–128, 291–294, 237–239 с.

9. Bassi A., Payot F., Suteau C. and Serre F. SAIGA feasibility studies: Study of the bundle degradation for the TIB scenario. Materials on NNC / CEA technical meeting – 2015 Sept 10.


Review

For citations:


Vityuk V.A., Vurim A.D., Kotov V.M., Vityuk G.A., Serre F., Payot F., Suteau C., Trotignon L. DEVELOPMENT OF A MODEL FA FOR THE STUDY OF EMERGENCY SITUATION WITH AN IMMEDIATE BLOCKING OF THE COOLANT FLOW IN FAST REACTOR. NNC RK Bulletin. 2018;(3):93-98. (In Russ.) https://doi.org/10.52676/1729-7885-2018-3-93-98

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ISSN 1729-7516 (Print)
ISSN 1729-7885 (Online)