Westinghouse Electric Company LLC

Pacific Nuclear Systems, Inc.

Peter M Newton

David W Wilson

John Michael Parke

John B Mason

Thomas J Gammon

Ronald Morris

Gregory D Paul

James M Wade

Steven K Hamilton

An emergency temporary spent fuel pool cooling system for a nuclear power generating facility that has a permanently installed primary loop within the nuclear containment and a mobile temporary secondary loop. The secondary loop is housed in transport vehicles that can be stored off site and is connectable in heat exchange relationship with the primary loop through quick disconnect couplings that are accessible on the outside of the reactor containment. The transport vehicles also include self-contained power and compressed air sources for powering and controlling the entire emergency cooling system. The system also has a make-up water injection capability for refueling the spent fuel pool and secondary loop.

Semi-portable emergency cooling system for removing decay heat from a nuclear reactor

A boiling water reactor is chemically decontaminated by circulating a decontamination solution through reactor recirculation loops and the annulus region of a reactor pressure vessel that surrounds the central core region while bypassing the central core region. The decontamination solution may also be circulated between the annulus region and a lower internals region while bypassing the central core region. The solution dissolves or breaks down metal oxide layers on the surfaces of the boiling water reactor. The metal oxide layers in the central core region and the activated metal ions contained in these layers, which do not substantially contribute to personnel exposure, are not released and, therefore, do not need to be removed from the solution.

Decontamination method

In combination with a nuclear power generating facility including a composite fuel pool including a reactor cavity and a spent fuel pool fluidly connectable to the reactor cavity, the composite fuel pool at least partially containing a primary fluid, a nuclear reactor vessel positioned in the reactor cavity, a residual heat removal system installed in the facility and fluidly connectable to the reactor vessel, and a spent fuel pool cooling system installed in the facility and fluidly connectable to the spent fuel pool, a temporary cooling system is provided, comprising a primary heat exchange system including a primary heat exchanger for transferring heat from a primary fluid to a secondary cooling fluid. The primary heat exchanger is temporarily locatable in the facility, and is temporarily fluidly connected to the composite fuel pool. A primary pump, also temporarily locatable in the facility, circulates primary fluid through the primary heat exchanger, which cools the primary fluid to a desired point at a faster rate than the spent fuel pool cooling system, allowing fuel to be immediately removed from the reactor rather than waiting for the residual heat removal system to cool the primary fluid to a point at which the spent fuel pool cooling system is able to provide adequate cooling capacity. Particulate filtration and demineralization may also be furnished with the system and method of the invention.

Temporary cooling system and method for removing decay heat from a

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Richland, WA, United States of America

Peter M Newton