Westinghouse Electric Company LLC

Siemens Westinghouse Power Corporation

Westinghouse Electric Sweden Ab

Dmitry V Paramonov

Mario D Carelli

William A Byers

Sture Helmersson

Zeses E Karoutas

Dennis A Horazak

Gunilla Norbäck

Milorad B Dzodzo

Carl Adamsson

Mahdi Majed

Rolf Eklund

Michael Y Young

Nelson J Zhan

Lawrence Green

The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product () and a method of operating a nuclear energy plant.

Method and apparatus of estimating dryout properties in a nuclear light water reactor

A crud-resistant nuclear fuel element cladding in which the axial locations that experience nucleate boiling during reactor full power operation are highly polished so that the maximum size of any surface defect on the highly polished surface is approximately 0.1 microns. The remainder of the cladding surface remains unpolished so that crud is more evenly redistributed over the entire fuel cladding surface to limit the thickness of the crud that is formed to less than 35 microns.

Crud-resistant nuclear fuel cladding

Hybrid combustion power systems comprising multiple direct energy conversion devices are disclosed, which devices ( ) are preferably combined with a Rankine cycle containing a steam turbine ( ), where combustion air (A) may be continuously preheated by an optional air heater ( ), then by the waste heat of a low temperature direct energy conversion device ( ) such as an alkali metal thermoelectric converter (AMTEC), and finally by the waste heat of a high temperature direct energy conversion device ( ) such as an AMTEC, where the AMTECs include electrolyte ( ) may include a condenser located in substantially the same geometrical plane as the AMTEC electrolyte ( ) and thermally insulated from the electrolyte.

Hybrid combustion power system

A unitary, transportable, assembled nuclear steam supply system (NSSS) with a lifetime fuel supply utilizes a fast or epithermal spectrum reactor core immersed in a pool of light water together with a plurality of steam generators through which the coolant is circulated by up to 100% natural circulation at full power, augmented by reactor coolant pumps also immersed in the pool. Redundant steam generators and reactor coolant pumps, together with the fast or epithermal spectrum reactor core and pool configuration, make it possible to operate the NSSS for 10 to 15 or more years without maintenance on the internals or refueling, thereby rendering the system proliferation resistant.

Unitary, transportable, assembled nuclear steam supply system with life time fuel supply and method of operating same

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Monroeville, PA, United States of America

Dmitry V Paramonov