Abstract: An improved apparatus and process for attaching welded omega seal segments to reactor heads, standpipes, mechanisms, and plugs comprises a first shank in combination with a second shank to attach an omega seal at a metal-to-metal interface.
Type:
Grant
Filed:
January 25, 1977
Date of Patent:
May 16, 1978
Assignee:
The United States of America as represented by the United States Department of Energy
Abstract: A pressure tap having utility in an environment of a solid-gas phase process flow includes a tubular coupling part having attached over a passage therethrough at an end opening thereof exposed to the flow a grating of spaced bars, and affixed internally across a passage therethrough so as to cover over an opening therein a screen which maintains contained within the passage between it and the grating a matrix of smooth spheres. The grating bars are so oriented by the disposition of the aforesaid end opening with respect to the flow such that accumulations of solids therebetween tending to bridge the opening are removed therefrom by the flow.
Type:
Grant
Filed:
October 17, 1973
Date of Patent:
May 9, 1978
Assignee:
The United States of America as represented by the United States Department of Energy
Abstract: A circular plate extends across the diameter of "sump suction" pump, with a close clearance between the edge of the plate and the wall of the pump tank. The plate is located above the pump impeller, inlet and outlet flow nozzles but below the sodium free surface and effectively divides the pump tank into two separate chambers. On change of pump speed, the close fitting flow restriction plate limits the rate of flow into or out of the upper chamber, thereby minimizing the rate of level change in the tank and permitting time for the pump cover gas pressure to be varied to maintain an essentially constant level.
Type:
Grant
Filed:
August 20, 1975
Date of Patent:
June 14, 1977
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration
Abstract: This invention is a fluid flow measuring device for determining the coolant flow at the entrance to a specific nuclear reactor fuel region. The device comprises a plurality of venturis having the upstream inlet and throat pressure of each respectively manifolded together to provide one static pressure signal for each region monitored. The device provides accurate flow measurement with low pressure losses and uniform entrance and discharge flow distribution.
Type:
Grant
Filed:
August 7, 1975
Date of Patent:
November 23, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration
Inventors:
Richard Atherton, Phillip S. Marinkovich, Peter R. Spadaro, J. Wilson Stout
Abstract: A cold trap assembly for removing impurities from a liquid metal being provided with a hole between the incoming impure liquid metal and purified outgoing liquid metal which acts as a continuous bleed means and thus prevents the accumulation of cover gases within the cold trap assembly.
Type:
Grant
Filed:
March 28, 1975
Date of Patent:
June 8, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration
Abstract: A positioning and locking device for fuel pin to grid attachment provides an inexpensive means of positively positioning and locking the individual fuel pins which make up the driver fuel assemblies used in nuclear reactors. The device can be adapted for use with a currently used attachment grid assembly design and insures that the pins remain in their proper position throughout the in-reactor life of the assembly. This device also simplifies fuel bundle assembly in that a complete row of fuel pins can be added to the bundle during each step of assembly.
Type:
Grant
Filed:
July 15, 1974
Date of Patent:
April 20, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration
Abstract: A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor pressure vessel, the core support grid structure or other in-core components and the opposite end located in heat transfer relationship with a heat exchanger having heat transfer fluid therein. The heat exchanger is located external to the pressure vessel whereby excessive core heat is transferred from the above reactor components and dissipated within the heat exchanger fluid.
Type:
Grant
Filed:
November 28, 1973
Date of Patent:
January 27, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration