EDN: GRMXKZ
Authors & Affiliations
Kartanov S.A., Korablev S.A., Pikulev A.A., Pluzyan K.G., Tkachenko D.N., Lopukhov N.V.
Federal state unitary enterprise “Russian Federal Nuclear Center – All-Russia Scientific Research Institute of Experimental Physics”, Sarov, Russia
Lopukhov N.V. – Junior Researcher. Contacts: 37, Mira st., Sarov, Nizhni Novgorod region, Russia, 607188. E-mail:
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Кartanov S.A. – Head of Science and Research Department, Cand. Sci. (Phys.-Math.).
Korablev S.A. – Research Engineer, 3d category.
Pikulev А.А. – Head of Science and Research Department.
Pluzyan K.G. – Head of Science and Research Laboratory.
Тkachenko D.N. – Research Engineer, 3d category.
Abstract
In the current paper there are presented the results of comprehensive calculation research of a promising pulsed nuclear reactor (PNR) that represents extension of water pulsed reactor (WPR) progress. For estimated characterization of pulse and loads on reactor vessel there is developed a mathematical model of fuel solution dynamics that makes it possible to take into account radial displacement of solution related to inhomogeneous distribution of energy release over the core volume and to the change of the vessel cross-section by height. There was performed a complex of calculations of the reactor vessel stress-deformed state in order to increase its strength characteristics for two operation modes: pulsed mode (dynamic loads) and long-term static mode (thermomechanical loads).
Calculations of the stress-strain state of the vessel of the core INR VIR-3 during the operation of the reactor in a pulsed mode showed that when a fission pulse is generated, the maximum stresses occur at the bends of the through central channel (SCC), at the point where the SCC is attached to the vessel bottom, in the upper part of the rod channels (SC) and SCC and in the places where the positioning dissecting grids are attached to the SCC, as well as the margin of safety of the vessel of the core when the reactor is operating in a pulsed mode in terms of yield strength is at least 3.5.
When operating in a long-term static mode, the maximum stresses occur in the places of the inflection of the SCC and in the place where the SCC is attached to the bottom of the vessel, he safety margin of the pressure vessel when the reactor is operating in a long-term static mode in terms of yield strength is at least 1.7, which meets the requirements of the rules.
The design of the vessel of the core INR VIR-3 satisfies all the necessary strength conditions both when the reactor is operating in a pulsed mode, and when the reactor is operating at a power of 20 kW in a long-term static mode.
Keywords
сomprehensive calculation research, core, promising nuclear reactor, mathematical model, fuel solution dynamics, energy release, reactor vessel, optimization calculations, strength properties, pulse mode, long-term static mode, fuel solution, stress-deformed state
Article Text (PDF, in Russian)
References
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UDC 539.411.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:4
