ROBERT A DELUCA
Engineering in Newton, MA

4737337, Apr 12, 1988

Feb 27, 1986

6/834196

George Garabedian - Boston MA
Robert A. DeLuca - Newton Centre MA

Stone & Webster Engineering Corporation - Boston MA

G21C 1518

376299

A nuclear reactor is provided characterized by a circulating liquid metal cooling system comprising a heat exchanger having a closed intermediate heat transfer fluid circuit in the form of a helical coil juxtaposed with the liquid metal coolant system, which effectively transfers heat through the intermediate circuit to a secondary fluid circuit. The intermediate heat transfer fluid circuit, which completely separates the liquid metal cooling system from the secondary fluid circuit, prevents potentially dangerous reactions between the primary liquid metal coolant and the secondary fluid (e. g. , water). The efficiency, reliability and safety of the heat exchanger features eliminates the need for many secondary heat removal and emergency components in the design of the nuclear reactor.

4737338, Apr 12, 1988

May 7, 1986

6/860552

George Garabedian - Boston MA
Robert A. DeLuca - Newton Centre MA

Stone & Webster Engineering Corp. - Boston MA

G21C 1928, G21C 1700

376402

Disclosed is a nuclear reactor employing a liquid metal and containing a reactor vessel, and at least one satellite vessel, and a hot and a cold leg connecting means which combine to form a continuous pathway for the flow of the liquid metal between the reactor vessel and the at least one satellite vessel. Each of the hot leg and cold leg connecting means contain a bellows assembly which are readily accessible for repair or replacement without draining the reactor vessel of the liquid metal.

4644906, Feb 24, 1987

May 9, 1985

6/732369

George Garabedian - Boston MA
Robert A. DeLuca - Newton Centre MA

Stone & Webster Engineering Corp. - Boston MA

F22B 102, F22B 3724

122 32

A double tube helical coil steam generator is provided in which a multiplicity of inner tubes conducting water are individually surrounded by outer tubes containing liquid metal as a heat transfer agent. The double tubes form into helical coils, providing a large surface area while conserving space. Immersion of the double tube helical coil in hot liquid metal, e. g. , from the core of a nuclear reactor, causes efficient transfer of heat across the liquid metal in the outer tube to the water in the inner tube, creating superheated steam, which can be cycled to a turbine and converted to electrical power. The efficiency, reliability and safety of the multiple double tube design of the steam generator obviates the necessity of many secondary heat removal and emergency components in addition to conserving space and material.

4765948, Aug 23, 1988

Aug 29, 1986

6/902228

Robert A. DeLuca - Newton Centre MA
George Garabedian - Boston MA

Stone & Webster Engineering Corporation - Boston MA

G21C 1524, H02K 4402, G21D 104

376404

A liquid metal circulation system is disclosed which is suitable for use in connection with a nuclear reactor. The circulation system of the invention includes an electromagnetic pump having a central core body featuring a helically configured, six pole magnet, optionally directing flow to one or a series of flow couplers, which generates sufficient liquid metal flow to be used as the primary circulation means for the nuclear reactor. The increased safety, design simplicity, and efficiency of such circulation system overcomes many of the drawbacks of conventional circulation systems.

4753773, Jun 28, 1988

Dec 26, 1985

6/813598

George Garabedian - Boston MA
Robert A. DeLuca - Newton Centre MA

Stone & Webster Engineering Corporation - Boston MA

G21C 1500, F22B 102, F22B 3724

376299

A double tube modular coil steam generator is provided in which a multiplicity of inner tubes conducting water are individually surrounded by outer tubes containing liquid metal as a heat transfer agent. The double tubes form into coils, providing a large surface area while conserving space. Immersion of the double tube coil in hot liquid metal, e. g. , from the core of a nuclear reactor, causes efficient transfer of heat across the liquid metal in the outer tube to the water in the inner tube, creating superheated steam, which can be cycled to a turbine and converted to electrical power. The efficiency, reliability and safety of the multiple double tube design of the steam generator obviates the necessity of many secondary heat removal and emergency components in addition to conserving space and material. The modular design allows ease of operation, fabrication and repair.

4786462, Nov 22, 1988

Feb 21, 1984

6/582016

George Garabedian - Boston MA
Robert A. DeLuca - Newton Center MA
George A. Gurnis - Cohasset MA
William C. Craig - Cambridge MA
James M. Barker - Reading MA

Stone & Webster Engineering Corp. - Boston MA

G21C 1300

376293

A novel concrete core support structure for nuclear reactors is described.