HOWARD W YANT
Engineers in Greensburg, PA

4703936, Nov 3, 1987

Nov 13, 1984

6/670789

Roy A. Clark - Mt. Lebanon PA
Howard W. Yant - Greensburg PA

Westinghouse Electric Corp. - Pittsburgh PA

F16J 1500, F16J 1546, G21C 1920

277 1

A sealoff device and method are disclosed for controlling the level of a fluid within first and second confined regions which are arranged in fluid communication with one another. In the preferred embodiment, the invention permits shielding of the tube bundle contained within the wrapper of a nuclear steam generator while controlling the level of the working fluid within the surrounding annular downcomer passage. A sealoff device constructed of a flexible hollow tube is provided in sealing engagement between the wrapper and outer shell forming the downcomer passage to provide a substantially fluid-tight seal thereat. The sealoff device permits the maintaining of a high water level inside the wrapper to shield the tube bundle which is emitting nuclear radiation while maintaining a low water level within the downcomer passage to permit greater accessibility for repair and maintenance of the steam generator in a dry environment and to permit greatly increased working time in a greatly reduced radiation field.

4135974, Jan 23, 1979

May 17, 1974

5/471068

Hans D. Garkisch - Irwin PA
Howard W. Yant - Greensburg PA
John F. Patterson - Murrysville PA

Westinghouse Electric Corp. - Pittsburgh PA

G21C 900, G21C 1900

176 87

A structural support system for the core of a nuclear reactor which achieves relatively restricted clearances at operating conditions and yet allows sufficient clearance between fuel assemblies at refueling temperatures. Axially displaced spacer pads having variable between pad spacing and a temperature compensated radial restraint system are utilized to maintain clearances between the fuel elements. The core support plates are constructed of metals specially chosen such that differential thermal expansion produces positive restraint at operating temperatures.

4032401, Jun 28, 1977

Aug 2, 1974

5/494431

Reinhard Froelich - Scottdale PA
Howard W. Yant - Greensburg PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 722

176 86R

A control system for a nuclear reactor comprising hollow mechanically operated control rods and a liquid neutron absorber which may be circulated through the hollow control rods. The liquid neutron absorber provides the nuclear reactor with a redundant safety system to deactivate the reactor.

4050985, Sep 27, 1977

Sep 13, 1974

5/505891

Howard W. Yant - Greensburg PA
Karl W. Stinebiser - New Stanton PA
Gregory C. Anzur - Herminie PA

Westinghouse Electric Corporation - Pittsburgh PA

G21C 1526

176 61

A nuclear reactor, particularly a liquid-metal breeder reactor, whose upper internals include outlet modules for channeling the liquid-metal coolant from selected areas of the outlet of the core vertically to the outlet plenum. The modules are composed of a highly-refractory, high corrosion-resistant alloy, for example, INCONEL-718. Each module is disposed to confine and channel generally vertically the coolant emitted from a subplurality of core-component assemblies. Each module has a grid with openings, each opening disposed to receive the coolant from an assembly of the subplurality. The grid in addition serves as a holdown for the assemblies of the corresponding subplurality preventing their excessive ejection upwardly from the core. In the region directly over the core the outlet modules are of such peripheral form that they nest forming a continuum over the core-component assemblies whose outlet coolant they confine. Each subassembly includes a chimney which confines the coolant emitted by its corresponding subassemblies to generally vertical flow between the outlet of the core and the outlet plenum.