Terrapower, LLC

Lawrence Livermore National Security, LLC

Other

Kevin J Kramer

Anselmo T Cisneros, Jr

Jeffery F Latkowski

Charles Gregory Freeman

Bassem S El-Dasher

Andrew James Bayramian

Ryan Abbott

Jon David McWhirter

Brian C Kelleher

Mark A Havstad

Daniel Flowers

Robert C Petroski

Joshua C Walter

Christopher J Johns

James A Demuth

Anselmo T Cisneros

Joseph Collin Farmer

Robert Alan Corbin

Ken Czerwinski

William M Kerlin

Jon D Mcwhirter

Jesse R Cheatham, Iii

James A DeMuth

Alexander M Rubenchik

John R Suyes, Iii

Ryan Abbot

John Rogers Gilleland

Pavel Hejzlar

Mark R Werner

Edward Ira Moses

James M Vollmer

Philip M Schloss

Christopher A Martin

Christopher M Regan

Kent E Wardle

James Andrew Roecker

John C Post

Daniel J Walter

Brian Morris

Eric P Storm

Tomas Diaz De La Rubia

Brain C Kelleher

Jr Anselmo T Cisneros

John R Suyes

Dan Flowers

Iii Jesse R Cheatham

Jeffrey F Latkowski

Jesse R Iii Cheatham

Robert A Corbin

Ryan Jr Abbot

Jesse R Cheatham

Ryan P Abbott

An integrated energy system includes a nuclear thermal plant situated on a nuclear site. The nuclear thermal plant produces thermal energy that is transported to a thermal energy storage system located outside the nuclear site. The thermal storage system is thermally coupled to a power generation system which is also remote to the nuclear site. By this arrangement, the nuclear thermal plant is isolated and decoupled from the power generation system. The nuclear thermal plant may supply thermal energy upwards of 800° C. or more to be stored at the thermal energy storage system until needed such as for industrial heat, power generation, or other uses. The thermal storage system is source agnostic, and one or more additional thermal energy generators, such as additional nuclear reactors, solar thermal plants, or other thermal energy generators can be coupled to a common thermal storage system and power generation system.

Thermal energy storage system connected to both a nuclear reactor and a power generator

An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active 'protecting isotopes' (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.

Anti-proliferation safeguards for nuclear fuel salts

A molten fuel salt nuclear reactor core assembly including a fluid neutron reflecting material defining a fast spectrum fuel volume configured to breed fissile fuel from fertile fuel, a first inlet channel, and a first outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume. The core assembly also includes a set of neutron absorbing members sized to fit within the fast spectrum fuel volume. The set of neutron absorbing members define a thermal spectrum fuel volume for a fission reaction of the fissile fuel, a second inlet channel, and a second outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.

Molten fuel nuclear reactor

A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.

Reflectors for molten chloride fast reactors

This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.

Direct reactor auxiliary cooling system for a molten salt nuclear reactor

A method is disclosed for manufacturing a part via an additive manufacturing process. A solution is used which has a volatile component within which is suspended particles of a powdered material. The solution is heated until it at least one of begins boiling or is about to begin boiling. The heated solution is then deposited at least at one location on a substrate to help form a layer of the part. The volatile component then evaporates, leaving only the particles of powdered material. The particles are then heated to the melting point. The deposition and heating operations are repeated to successively form a plurality of layers for the part. The evaporation of the volatile component helps to cool the part.

System and method for forming material substrate printer

Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.

Molten fuel reactor thermal management configurations

A molten chloride fast reactor (MCFR) includes a plurality of reflectors defining a central core having a core geometric center. A flow channel fluidically connected to the central core. The flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core. A primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel. The MCFR also includes a decay heat heat exchanger (DHHX). At least a portion of the DHHX is disposed above the core geometric center, and a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.

Direct heat exchanger for molten chloride fast reactor

Sodium-tin and sodium-tin-lead compositions have been identified and created that exhibit better reactivity characteristics (i.e., are less reactive) than sodium metal under the same conditions, making these compositions safer alternatives to sodium metal for use as a coolant. These compositions include compositions having at least 90% sodium (Na), from 0-10% lead (Pb) and the balance being tin (Sn).

Sodium-tin and sodium-tin-lead coolants

The present disclosure relates to a method of producing a product through additive manufacturing with heat treatment. The method involves using a fusing beam to melt powder particles disposed on a substrate, where the fusing beam is impressed with a two dimensional pattern containing image information from a first layer to be printed. The fused powder particles are then heat treated with a beam impressed with an additional two dimensional pattern. The additional two dimensional pattern has image information from the first layer to achieve heat treatment of the product. The heat treatment is completed prior to laying down additional new layers of material. The heat treatment is an annealing operation. The method may further involve providing a new layer of powdered material on top of the layer of fused powder particles subsequent to the heat treatment, and repeating the melting and heat treating operations in a layer-by-layer fashion using the two dimensional pattern and the additional two dimensional pattern, until the part is completed.

Heat treatment to anneal residual stresses during additive manufacturing

Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around a reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described. A further configuration is described that utilizes a core barrel between a reactor core volume of molten fuel salt and a reflector volume, in which the reflector volume contains a plurality of individual reflector elements separated by an interstitial space filled with molten fuel salt.

Molten fuel nuclear reactor with neutron reflecting coolant

A system of 3D printing using a high temperature 3D print head that functions as a 'modified ink jet' printer. The print head has the ability to print high temperature material such as metal, silicon carbide, and other high temperature material as opposed to inks or plastics. The print head is fabricated from a high temperature material to maintain structural integrity while operation at temperatures above the melting temperature for the material that is being printed.

High temperature additive manufacturing print head

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Pleasanton, CA, United States of America

Kevin J Kramer