The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Jul. 16, 2019

Filed:

Oct. 26, 2015
Applicant:

Nuscale Power, Llc, Corvallis, OR (US);

Inventors:

Michael Keller, Corvallis, OR (US);

Ross Snuggerud, Corvallis, OR (US);

Tamas Liszkai, Corvallis, OR (US);

Assignee:

NUSCALE POWER, LLC, Corvallis, OR (US);

Attorney:
Primary Examiner:
Assistant Examiner:
Int. Cl.
CPC ...
G21C 15/18 (2006.01); G21C 13/02 (2006.01); G21C 15/24 (2006.01); G21C 17/00 (2006.01); G21C 13/00 (2006.01);
U.S. Cl.
CPC ...
G21C 15/18 (2013.01); G21C 13/00 (2013.01); G21C 13/02 (2013.01); G21C 15/24 (2013.01); G21C 17/00 (2013.01); Y02E 30/40 (2013.01);
Abstract

A cooling system for a reactor module includes a reactor pressure vessel that houses primary coolant and a steam generator that lowers a temperature of the reactor pressure vessel by transferring heat from the primary coolant to a secondary coolant. The steam generator releases at least a portion of the secondary coolant as steam. Additionally, the cooling system includes a containment vessel that at least partially surrounds the reactor vessel in a containment region. The containment region is dry during normal operation of the reactor module. A controller introduces a source of water into the containment region in response to a non-emergency shut down of the reactor module. The source of water is located external to the containment vessel, and the water is introduced into the containment region after the steam generator has initially lowered the temperature of the reactor pressure vessel in response to releasing the steam.


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