Combination reactor gamma radiation power harvesting reactor power distribution measurement, and support to coolant freezing protection system for liquid metal and molten salt-cooled reactor systems
US-2019385758-A1 · Dec 19, 2019 · US
US11715577B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-11715577-B2 |
| Application number | US-202117191324-A |
| Country | US |
| Kind code | B2 |
| Filing date | Mar 3, 2021 |
| Priority date | Mar 3, 2021 |
| Publication date | Aug 1, 2023 |
| Grant date | Aug 1, 2023 |
A practical reading order for non-experts. Skip the full description unless you need deep technical detail.
What the patent document calls the invention.
A short plain-language summary of the technical disclosure.
Who owns or filed the patent and who is credited as inventor.
Filing, priority, publication, and grant dates set the timeline.
The legal scope of protection — read this for what is actually claimed.
Technology tags used to group this patent with similar filings.
Prior art links and similar publications in this corpus.
Official abstract text for this publication.
A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.
Opening claim text (preview).
What is claimed is: 1. A neutron detector comprising: a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity, and wherein the housing is configured to prevent a traversal of electrons; an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons; and an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor. 2. The neutron detector of claim 1 , wherein the electron emissive material is dispositioned between the housing and the neutron sensitive material. 3. The neutron detector of claim 2 , further comprising an electrically insulating material is dispositioned between the electron emissive material and the housing. 4. The neutron detector of claim 3 , wherein the current of electrons is configured to traverse through the cavity, and wherein the electrically insulating material is configured to allow the traversal of the current of electrons. 5. The neutron detector of claim 4 , further comprising a signal lead configured to generate a signal associated with the current of electrons. 6. The neutron detector of claim 5 , wherein the signal lead is configured to electrically power a transmitter via the current of electrons, and wherein the transmitter configured to transmit the signal generated by the signal lead. 7. The neutron detector of claim 6 , wherein the transmission is wireless. 8. The neutron detector of claim 1 , wherein the amount of neutron sensitive material is determined based, at least in part, on a desired sensitivity of the neutron detector. 9. The neutron detector of claim 1 , wherein the amount of neutron sensitive material is determined based, at least in part, on a desired length of life of the neutron detector. 10. The neutron detector of claim 1 , wherein the amount of electron emissive material is determined based, at least in part, on a desired sensitivity of the neutron detector. 11. The neutron detector of claim 1 , wherein the amount of electron emissive material is determined based, at least in part, on a desired length of life of the neutron detector. 12. A system configured to detect neutrons, comprising: a neutron detector comprising: a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity, and wherein the housing is configured to prevent a traversal of electrons; an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons; and an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor; and a signal lead configured to generate a signal associated with the current of electrons; and a monitoring subsystem communicably coupled to the neutron detector, wherein the monitoring subsystem comprises a control circuit configured to: receive the signal generated by the signal lead; determine a magnitude of the current of electrons based, at least in part, on the signal received from the signal lead; and determine the amount of neutrons emitted from the core of the nuclear reactor based, at least in part, on the determined magnitude of the current of electrons. 13. The system of claim 12 , wherein the control circuit is further configured to: determine a neutron flux of the nuclear reactor based, at least in part, on the determined amount of neutrons emitted from the core of the nuclear reactor; and determine a power output of the nuclear reactor based, at least in part, on the determined neutron flux of the nuclear reactor. 14. The system of claim 12 , further comprising a transmitter electrically coupled to the signal lead, wherein the transmitter is configured to transmit the signal generated by the signal lead. 15. The system of claim 14 , wherein the signal lead is configured to electrically power the transmitter via the current of electrons. 16. The neutron detector of claim 12 , wherein the electron emissive material is dispositioned between the housing and the neutron sensitive material. 17. The system of claim 16 , wherein the neutron detector further comprises an electrically insulating material is dispositioned between the electron emissive material and the housing. 18. A method of detecting neutrons emitted from a core of a nuclear reactor, the method comprising: causing an interaction between an amount of neutrons emitted from the core and a neutron sensitive material; generating, via the interaction, gamma rays to be emitted towards an electron emissive material; causing an interaction between the emitted gamma rays and the electron emissive material; generating, via the interaction, a current of electrons indicative of the amount of neutrons emitted from the core; determining a magnitude of the generated current of electrons; and determining the amount of neutrons emitted from the core based, at least in part, on the determined magnitude of the generated current of electrons. 19. The method of claim 18 , further comprising: determining a neutron flux of the nuclear reactor based, at least in part, on the determined amount of neutrons emitted from the core; and determining a power output of the nuclear reactor based, at least in part, on the determined neutron flux. 20. The method of claim 18 , further comprising: generating a signal associated with the generated current of electrons; and transmitting the signal generated by the signal lead to a receiver for further processing.
accompanied by nuclear fission · CPC title
Measuring neutron radiation (G01T5/00 takes precedence) · CPC title
Monitoring; Testing (measuring in general G01); {Maintaining} · CPC title
using self-powered detectors (for neutrons as well as for Y- or X-rays), e.g. using Compton-effect (Compton diodes) or photo-emission or a (n,B) nuclear reaction (radioisotopic generators G21H1/00, e.g. G21H1/02, G21H1/04; photo-tubes H01J40/00; thermionic generators H01J45/00) · CPC title
Measuring reactor flux · CPC title
Related publications grouped by family.
Answers are generated from the same data shown on this page.