Thermal Hydraulics Verification Safety Studies to Support the Licensing of Neutron Source Accelerator Driven System

O. V. Kukhotskyi1, A. V. Nosovskyi2

1SE “State Scientific and Technical Center for Nuclear and Radiation Safety”,
35-37, V. Stusa st., Kyiv, 03142, Ukraine
2Institute for Safety Problems of Nuclear Power Plants, NAS of Ukraine,
12, Lysogirska st., Kyiv, 03028, Ukraine

DOI: doi.org/10.31717/2311-8253.20.1.4

Abstract

The State Scientific and Technical Center for Nuclear and Radiation Safety performs the scientific and technical support of Ukrainian regulatory authority (State Nuclear Regulatory Inspectorate of Ukraine) in licensing activities of the Neutron Source Based on a Subcritical Assembly Driven by a Linear Electron Accelerator (hereinafter designated as the Neutron Source). In the Neutron Source’s licensing, the independent models of key nuclear facility elements were developed and calculations for verification safety studies using non-identical analytical tools were performed.
Aspects related to the development of independent (regulatory) thermal hydraulics models of the core elements of the Neutron Source are discussed in the paper. The process of modeling neutron-generating target and the fuel assembly of Neutron Source are described in the article. Moreover, the results of the verification safety studies are also presented.

Keywords: thermal-hydraylics, safety studies, licensing process, neutron source, accelerator driven.

References

1. General Safety Provisions for Nuclear Subcritical Assembly: NP 306.2.183-2012. SNRIU, 2 012. (in Ukr.)

2. Gashev M. Kh., Grigorash O. V., Dolotov A. V., Nosovskyi A. V., Dybach O. M., Berezhnoi A. I., Kukhotskyi O. V. (2013). [Licensing of the Neutron Source Based on the Subcritical Assembly Driven by a Linear Electron Accelerator]. Yaderna ta Radyiatsyijna Bezpeka [Nuclear and radiation safety], no. 4, pp. 3-9. (in Russ.)

3. Nuclear Subcritical Facility “Neutron Source Based on the Subcritical Assembly Driven by a Linear Electron Accelerator”. PSAR — KIPT, 2012. (in Russ.)

4. Kukhotsky O. V., Nosovskyi A. V., Dybach O. M. (2017). Development of thermohydraulic models of core elements of “Neutron source”. Problems of Atomic Science and Technology, no. 2, pp. 131-137.

5. The Overview of the Existing Models Applied for Neutron Source Verification Calculations. Report TB3-A3 INSC Project U3.01/12 (UK/TS/49). SSTC NRS, 2016.

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Published
2020-02-29

If the article is accepted for publication in the journal «Industrial Heat Engineering» the author must sign an agreement on transfer of copyright. The agreement is sent to the postal (original) or e-mail address (scanned copy) of the journal editions.

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