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CONVERTER OF IGR NEUTRONS FOR TESTING OF FAST REACTORS FUEL ELEMENTS

https://doi.org/10.52676/1729-7885-2018-4-18-21

Abstract

One of the ways to develop the nuclear industry is to improve the technology of fast reactors. For these purposes it is necessary to carry out experiments with fuels of fast reactors. However, in a thermal reactor such as GGR, it is difficult to obtain a uniform flux of fast neutrons. One of the options for reducing the unevenness of fast neutrons flux is the proposed device – a neutron converter, capable of solving this problem.

About the Authors

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


O. M. Zhanbolatov
Branch “Institute of Atomic Energy” RSE NNC RK
Kazakhstan
Kurchatov


References

1. Витюк Г.А., Котов В.М., Витюк В.А., Жанболатов О.М. Расчет теплогидравлических параметров испытаний топлива быстрого реактора со свинцово - висмутовым теплоносителем. – Вестник НЯЦ РК, вып. 3, 2016, стр. 77–85.

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

3. Вурим А.Д., Котов В.М., Иркимбеков Р.А., Жагипарова Л.К., Байгожина А.А. Компьютерная модель реактора ИГР для стационарных нейтронно-физических расчетов. – А.с. № 2738 РК, 27.12.2016.

4. Котов В.М., Жанболатов О.М. Конвертер нейтронов ИГР для испытаний твэлов быстрых реакторов. – Вестник НЯЦ РК, вып. 1, 2017, стр. 98–101.

5. V.M. Kotov, A.S. Sergeeva, R.A. Irkimbekov, V.I. Suprunov. The Possibilities of Fission Material Reproduction Increase in Thermal Reactor with the Assemblies with a Hard Neutron Spectrum/ Science and Technology of Nuclear Installations. 2011.


Review

For citations:


Kotov V.M., Zhanbolatov O.M. CONVERTER OF IGR NEUTRONS FOR TESTING OF FAST REACTORS FUEL ELEMENTS. NNC RK Bulletin. 2018;(4):18-21. (In Russ.) https://doi.org/10.52676/1729-7885-2018-4-18-21

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