US 11,798,694 B2
Molten fuel nuclear reactor
Anselmo T. Cisneros, Jr., Seattle, WA (US); Charles Gregory Freeman, Kirkland, WA (US); Kevin Kramer, Redmond, WA (US); and Jeffery F. Latkowski, Mercer Island, WA (US)
Assigned to TerraPower, LLC, Bellevue, WA (US)
Filed by TerraPower, LLC, Bellevue, WA (US)
Filed on Oct. 21, 2020, as Appl. No. 17/76,309.
Application 17/076,309 is a division of application No. 15/783,895, filed on Oct. 13, 2017, granted, now 10,867,710, issued on Dec. 15, 2020.
Application 15/783,895 is a continuation in part of application No. 15/584,684, filed on May 2, 2017, granted, now 10,665,356, issued on May 26, 2020.
Application 15/584,684 is a continuation in part of application No. 15/282,814, filed on Sep. 30, 2016, granted, now 10,734,122, issued on Aug. 4, 2020.
Claims priority of provisional application 62/337,235, filed on May 16, 2016.
Claims priority of provisional application 62/330,726, filed on May 2, 2016.
Claims priority of provisional application 62/234,889, filed on Sep. 30, 2015.
Prior Publication US 2021/0210224 A1, Jul. 8, 2021
Int. Cl. G21C 7/28 (2006.01); G21C 3/54 (2006.01); G21C 7/22 (2006.01); G21C 7/27 (2006.01); G21C 1/02 (2006.01); G21C 1/22 (2006.01); G21C 15/28 (2006.01); G21C 1/32 (2006.01); G21C 11/06 (2006.01); G21C 15/02 (2006.01)
CPC G21C 7/28 (2013.01) [G21C 3/54 (2013.01); G21C 7/22 (2013.01); G21C 7/27 (2013.01); G21C 1/026 (2013.01); G21C 1/22 (2013.01); G21C 1/326 (2013.01); G21C 11/06 (2013.01); G21C 15/02 (2013.01); G21C 15/28 (2013.01); Y02E 30/30 (2013.01)] 6 Claims
OG exemplary drawing
 
1. A molten fuel salt nuclear reactor core assembly comprising:
a set of neutron reflectors, the set of neutron reflectors defining a fast spectrum fuel volume and at least one reflector fuel inlet channel and at least one reflector fuel outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume; and
a set of neutron absorbing members sized to fit within the fast spectrum fuel volume, the set of neutron absorbing members defining a thermal spectrum fuel volume, and at least one absorber fuel inlet channel and at least one absorber fuel outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.