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:
Nov. 09, 2021

Filed:

Oct. 07, 2019
Applicant:

Terrapower, Llc, Bellevue, WA (US);

Inventors:

Jesse R. Cheatham, III, Seattle, WA (US);

Anselmo T. Cisneros, Jr., Seattle, WA (US);

Jeffery F. Latkowski, Mercer Island, WA (US);

James M. Vollmer, Kirkland, WA (US);

Christopher J. Johns, Tocoma, WA (US);

Assignee:

TerraPower, LLC, Bellevue, WA (US);

Attorney:
Primary Examiner:
Int. Cl.
CPC ...
G21C 19/28 (2006.01); G21C 7/30 (2006.01); G21C 1/22 (2006.01); G21C 3/24 (2006.01); G21C 1/03 (2006.01); G21C 3/54 (2006.01); G21C 15/28 (2006.01); G21C 19/30 (2006.01); G21C 19/50 (2006.01); G21C 19/303 (2006.01); G21C 19/20 (2006.01); G21C 17/104 (2006.01); G21C 3/22 (2006.01);
U.S. Cl.
CPC ...
G21C 7/30 (2013.01); G21C 1/03 (2013.01); G21C 1/22 (2013.01); G21C 3/24 (2013.01); G21C 3/54 (2013.01); G21C 15/28 (2013.01); G21C 19/28 (2013.01); G21C 19/30 (2013.01); G21C 19/303 (2013.01); G21C 19/50 (2013.01); G21C 3/22 (2013.01); G21C 17/104 (2013.01); G21C 19/205 (2013.01); Y02E 30/30 (2013.01);
Abstract

A molten salt reactor includes a nuclear reactor core for sustaining a nuclear fission reaction fueled by a molten fuel salt. A molten fuel salt control system removes a volume of the molten fuel salt from the nuclear reactor core to maintain a reactivity parameter within a range of nominal reactivity. The molten fuel salt control system includes a molten fuel salt exchange system that fluidically couples to the nuclear reactor core and exchanges a volume of the molten fuel salt with a volume of a feed material containing a mixture of a selected fertile material and a carrier salt. The molten fuel salt control system can include a volumetric displacement control system having one or more volumetric displacement bodies insertable into the nuclear reactor core. Each volumetric displacement body can remove a volume of molten fuel salt from the nuclear reactor core, such as via a spill-over system.


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