A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.

A super plant comprises absolute technologies an ultra-transport system, an ultra-cycling light fluids bulk power electromagnetic fluids creep, stiffness precise balancing displacements energy, minimum energy balancing, minimal energy displacements for cosmological global gravitational dynamics conforming nullities relativity energy cycles to energy relativity structures comprising: means for opposing global air warming, affecting Heat Rate maximum efficiencies of the ultra-transport system, Regions 1-5 ultra-longevity boundaries ultra-fluxing, ultra-conserving the bulk power, the mega bulk power, boundaries perfections, and the magnetosphere mega bulk power Regions 4 portions mega bulk power portion.

A forever technologies ultimate energy device affecting energy dynamics planet genesis, gravity fields do: embodies sui generis boundaries perfections in ultimately compact structures, discerns, distinguishes forms of cycling energy genres, effectuates an energy form respective directionality and embraces energy cycling maximum conductance, or maximum ultimate Heat Rate efficiency or maximally, ultimately short paths-of-passage lengths' sums comprising a least sum (PPLSLS).

A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop.

A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop.

A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.

A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.

A compact pressurized water nuclear reactor having connected to the reactor pressure vessel a plurality of pressure vessels connected by nozzles, and connected by curved horizontal pressure vessel heads by having their central axis horizontal, with reduced stress and simple single connection between the respective nozzle of the reactor pressure vessel with the respective nozzle of each curved horizontal pressure vessel heads, all with the same internal and external design pressure.

A compact pressurized water nuclear reactor having connected to the reactor pressure vessel a plurality of pressure vessels connected by nozzles, and connected by curved horizontal pressure vessel heads by having their central axis horizontal, with reduced stress and simple single connection between the respective nozzle of the reactor pressure vessel with the respective nozzle of each curved horizontal pressure vessel heads, all with the same internal and external design pressure.

The present disclosure is directed to systems, devices and methods for cooling a surface with a plurality of ejectors. The fluid provided to the micro-ejectors includes vapor formed at the surface. The vapor provides the driving force for driving fluid through the micro-ejectors.