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Modeling the transport of nitrogen in an NPP-2006 reactor circuit

Content Provider	Springer Nature Link
Author	Stepav, O. E. Galkin, I. Yu. Sledkov, R. M. Melekh, S. S. Strebnev, N. A.
Copyright Year	2016
Abstract	Efficient radiation protection of the public and personnel requires detecting an accident-initiating event quickly. Specifically, if a heat-exchange tube in a steam generator is ruptured, the $^{16}$N radioactive nitrogen isotope, which contributes to a sharp increase in the steam activity before the turbine, may serve as the signaling component. This isotope is produced in the core coolant and is transported along the circulation circuit. The aim of the present study was to model the transport of $^{16}$N in the primary and the secondary circuits of a VVER-1000 reactor facility (RF) under nominal operation conditions. KORSAR/GP and RELAP5/Mod.3.2 codes were used to perform the calculations. Computational models incorporating the major components of the primary and the secondary circuits of an NPP-2006 RF were constructed. These computational models were subjected to cross-verification, and the calculation results were compared to the experimental data on the distribution of the void fraction over the steam generator height. The models were proven to be valid. It was found that the time of nitrogen transport from the core to the heat-exchange tube leak was no longer than 1 s under RF operation at a power level of 100% N $_{nom}$ with all primary circuit pumps activated. The time of nitrogen transport from the leak to the γ-radiation detection unit under the same operating conditions was no longer than 9 s, and the nitrogen concentration in steam was no less than 1.4% (by mass) of its concentration at the reactor outlet. These values were obtained using conservative approaches to estimating the leak flow and the transport time, but the radioactive decay of nitrogen was not taken into account. Further research concerned with the calculation of thermohydraulic processes should be focused on modeling the transport of nitrogen under RF operation with some primary circuit pumps deactivated.
Starting Page	511
Ending Page	515
Page Count	5
File Format	PDF
ISSN	00406015
Journal	Thermal Engineering
Volume Number	63
Issue Number	7
e-ISSN	15556301
Language	English
Publisher	Pleiades Publishing
Publisher Date	2016-06-23
Publisher Place	Moscow
Access Restriction	One Nation One Subscription (ONOS)
Subject Keyword	reactor facility VVER nitrogen heat-exchange tube leak steam generator KORSAR RELAP5 Engineering Thermodynamics, Heat and Mass Transfer
Content Type	Text
Resource Type	Article
Subject	Energy Engineering and Power Technology Nuclear Energy and Engineering

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