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Molten fuel nuclear reactor with neutron reflecting coolant

專(zhuān)利號(hào)
US10867710B2
公開(kāi)日期
2020-12-15
申請(qǐng)人
TerraPower, LLC(US WA Bellevue)
發(fā)明人
Anselmo T. Cisneros, Jr.; Charles Gregory Freeman; Kevin Kramer; Jeffery F. Latkowski
IPC分類(lèi)
G21C7/28; G21C3/54; G21C1/02; G21C7/22; G21C1/22; G21C15/28; G21C1/32; G21C7/27; G21C11/06; G21C15/02
技術(shù)領(lǐng)域
neutron,reflector,reactor,fuel,neutrons,in,core,flowing,material,molten
地域: WA WA Bellevue

摘要

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.

說(shuō)明書(shū)

One type of breed-and-burn reactor is a molten salt reactor (MSR). Molten salt reactors are a class of fast spectrum nuclear fission reactors wherein the fuel is a molten salt fluid containing mixed or dissolved nuclear fuel, such as uranium or other fissionable elements. In an MSR system, the unmoderated, fast neutron spectrum provided by fuel salts enables good breed performance using the uranium-plutonium fuel cycle. In contrast to the fast spectrum neutrons that dominate breeding of fissile fuel from fertile fuel, thermal neutrons dominate the fission reaction of fissile fuel. A fission reaction resulting from a collision of a thermal neutron with a nuclide can consume the fissile fuel in a fission reaction, releasing fast spectrum neutrons, gamma rays, large amounts of heat energy and expelling fission products, such as smaller nuclei elements. Consuming nuclear fuel is referred to as burnup or fuel utilization. Higher burnup typically reduces the amount of nuclear waste remaining after the nuclear fission reaction terminates. The fast neutron spectrum also mitigates fission product poisoning to provide exceptional performance without online reprocessing and the attendant proliferation risks. The design and operating parameters (e.g., compact design, low pressures, high temperatures, high power density) of a breed-and-burn MSR, therefore, offer the potential for a cost-effective, globally-scalable solution to zero carbon energy.

Molten Fuel Nuclear Reactor with Neutron Reflecting Coolant

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