Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Ponya, Petra ✉; Csom, Gyula [Csom, Gyula (Magenergetikai be...), szerző] Nukleáris Technikai Intézet (BME / TTK); Feher, Sandor [Fehér, Sándor (reaktorfizika), szerző] Nukleáris Technika Tanszék (BME / TTK / NTI)

Angol nyelvű Szakcikk (Folyóiratcikk) Tudományos
  • SJR Scopus - Nuclear Energy and Engineering: Q3
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Fast neutron irradiation causes embrittlement of the reactor pressure vessel (RPV) material; therefore, it may end operation life before design lifetime. Well-known method to recuperate crystal lattice dislocations is annealing. In the current version of thorium fueled supercritical water-cooled reactor (SCWR) design proposed by the Institute of Nuclear Technology at Budapest University of Technology and Economics (BME NTI), the supercritical fluid flows upward between the core barrel and the inner surface of the RPV thereby, the coolant would keep the RPV's temperature at similar to 500 degrees C. This reverse coolant flow direction would decrease the embrittlement of RPV by constant annealing. To minimize the fast neutron flux increase, a relatively thin shielding connected to the inner surface of the barrel could be used. This presents fast neutron irradiation analysis, performed for different settings of the shielding to reduce fast neutron flux reaching the inner surface of RPV.
Hivatkozás stílusok: IEEEACMAPAChicagoHarvardCSLMásolásNyomtatás
2022-09-27 16:28