摘要:
(57) Reflective type insulation is utilized to elevate the temperature in the loop seal piping of a loop seal of a pressurizer. Damage to safety valve components and downstream piping caused by water in the piping is substantially reduced by exposing the loop seal piping to heat gain from a portion of the outer surface of the pressurizer. Safety valve allowable sustained operating temperature requirements are considered in the insulation system design.
摘要:
A nuclear reactor is equipped with a cooling water circulation system (2) which includes a water-feed conduit and a drain conduit (5) to circulate the cooling water to and from a pressure vessel (12) which surrounds a reactor core (1), the cooling water having a free liquid level (13) maintained above the reactor core (1). The drain conduit (5) is inserted in the pressure vessel (12) from the upper side toward the lower side relative to free liquid level (13). A double tube (11) consisting of an inner tube (10) and an outer tube (14) maintaining a gap therebetween is formed in the end portion of the drain conduit (5). The inner tube (10) and outer tube (14) being continuous with the drain conduit (5), the opening (7) at the lower end of the inner tube (10) is located below said free liquid level (13) but above the reactor core (1). The opening (15) at the upper end of the outer tube (14) is located above free liquid level (13). The opening (16) at the lower end of said outer tube (14) is located below the reactor core (1).
摘要:
Réacteur nucléaire à eau légère (REL), notamment à eau pressurisée (REP) ou à eau bouillante (REB), à source froide au sol et intégrant un système autonome d'évacuation de la puissance résiduelle (EPUR). L'invention consiste essentiellement à implanter une machine ORC et une réserve d'eau supplémentaire, distincte de la piscine, l'énergie stockée dans la piscine étant la source chaude pour l'évaporateur de l'ORC, la réserve d'eau supplémentaire alimentant directement le condenseur de l'ORC par une pompe dédiée pour constituer la source froide au condenseur de l'ORC.
摘要:
A nuclear reactor decommissioning system according to an embodiment includes a cutting device to cut a reactor, a lifting device inserted inside the reactor to lift the reactor, and a shielding device that is positioned between the reactor and the lifting device and blocks radioactive dust generated by the cutting device from spreading.
摘要:
The core flow rate of a boiling water reactor (BWR) (19) is adjusted so that it reaches a core flow rate setting that is determined from the characteristic according to the ratio of Pu-239 in transuranic nuclides (TRU) included in a new fuel assembly (1) to be loaded in a core (20). The core flow rate is maintained at the set core flow rate in all operation cycles of the BWR (19). Accordingly, the ratios of a plurality of TRU isotopes included in a fuel assembly (1) when the fuel assembly (1) is taken out of the BWR core (20) as a spent fuel is substantially the same as the ratios of the plurality of TRU isotopes included in a new fuel assembly (1) to be loaded in the BWR core (20). The ratio of Pu-239 in TRU included in the new fuel assembly (1) is 3% or more but 45% or less. As a result, a nuclear proliferation resistance can be increased while restrictive conditions for safety are met, a burnup can be further increased, and TRU multi-recycling becomes feasible.
摘要:
A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (MI) cables, the MI cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their MI cables and for any underlying hydraulic lines.