# US 11,079,504 B2 · Differential neutron spectrum generator and related methods and systems > Agents: this data is available as JSON from the patentgrep API and MCP server — see https://patentgrep.com/llms.txt - Number: US 11,079,504 B2 - Document ID: US11079504B2 - Status: Granted - Kind: B2 - Application number: 15/971,767 - Filed: 2018-05-04 - Published: 2018-11-15 - Granted: 2021-08-03 - Earliest claimed: 2017-05-12 - Assignees: Battelle Energy Alliance, LLC - Applicants: Battelle Energy Alliance, LLC - Inventors: Wade Scates - Web page: https://patentgrep.com/patent/US11079504B2 ## CPC - G01T 7/005: {calibration techniques (stabilization of spectrometer G01T1/40)} - G01T 3/065: {Spectrometry} - G01T 3/085: {Spectrometry} - G21G 4/02: Neutron sources - H05H 3/06: Generating neutron beams (targets for producing nuclear reactions H05H6/00; neutron sources G21G4/02) - G01T: MEASUREMENT OF NUCLEAR OR X-RADIATION (radiation analysis of materials, mass spectrometry G01N23/00; tubes for determining the presence, intensity, density or energy of radiation or particles H01J47/00) - G21G: CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES (applications of radiation in general G21H5/00; handling particles, e.g. neutrons, or electromagnetic radiation not otherwise provided for G21K) - H05H: PLASMA TECHNIQUE (apparatus or processes specially adapted for producing X-rays H05G2/00); PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS ## Abstract A neutron spectrum generator is disclosed herein including a neutron source, a scatterer positioned in a direct path between the neutron source and a neutron detector, and a material shell configured to have at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum at the neutron detector that is different than the spectrum of the neutron source. A related method includes measuring a first response generated by a first material shell of a neutron spectrum generator interacting with a neutron source, replacing the first material shell with a second material shell, measuring a second response generated by a second material shell of a neutron spectrum generator interacting with the neutron source, and determining a total fission response by determining a difference between the first response and the second response. ## Claims ### Claim 1 A neutron spectrum generator, comprising: a neutron source; a scatterer positioned in a direct path between the neutron source and a neutron detector; and at least one material shell positioned proximate the neutron source, and configured with at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum responsive to interacting with neutrons that is different than a spectrum of the neutron source. ### Claim 2 (depends on 1) The neutron spectrum generator of claim 1, wherein the at least one material shell is a cylindrical shape. ### Claim 3 (depends on 1) The neutron spectrum generator of claim 1, wherein the at least one material shell is a hemispheric shape. ### Claim 4 (depends on 1) The neutron spectrum generator of claim 1, wherein the at least one material shell is a shape symmetric about its axis, wherein the axis is a vector extending from the neutron source through the scatterer to the neutron detector. ### Claim 5 (depends on 1) The neutron spectrum generator of claim 1, wherein the at least one non-uniform characteristic of the material shell is divided according to angular wedges of the material shell. ### Claim 6 (depends on 1) The neutron spectrum generator of claim 1, wherein the neutron source is a DT generator configured to produce neutrons by fusion of deuterium (D) and tritium (T). ### Claim 7 (depends on 1) The neutron spectrum generator of claim 1, wherein the neutron source is a DD generator configured to produce neutrons by fusion of deuterium (D) and deuterium (D). ### Claim 8 (depends on 1) The neutron spectrum generator of claim 1, wherein the neutron source is selected from the group consisting of a gamma source configured to eject a neutron, an electron accelerator beam, and a Bremsstrahlung converter. ### Claim 9 (depends on 1) The neutron spectrum generator of claim 1, wherein the at least one material shell includes multiple material shells. ### Claim 10 (depends on 9) The neutron spectrum generator of claim 9, wherein the multiple material shells are configured to generate the specific spectrum exhibiting multiple peaks. ### Claim 11 (depends on 1) The neutron spectrum generator of claim 1, wherein the specific spectrum is an approximation of the spectrum for Californium-252, and the neutron source is a different source than Californium-252. ### Claim 12 A method for generating a specific neutron spectrum, the method comprising: measuring a first response generated responsive to a first material shell of a neutron spectrum generator interacting with a neutron source; replacing the first material shell with a second material shell; measuring a second response generated responsive to the second material shell of a neutron spectrum generator interacting with the neutron source; and determining a total fission response by determining a difference between the first response and the second response. ### Claim 13 (depends on 12) The method of claim 12, further comprising forming the first material shell and the second material shell to each have at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum at a neutron detector that is different than a spectrum of the neutron source. ### Claim 14 (depends on 13) The method of claim 13, further comprising forming the first material shell and the second material shell to each have a cylindrical shape. ### Claim 15 (depends on 12) The method of claim 12, further comprising forming the first material shell including uranium and the second material shell including lead. ### Claim 16 (depends on 12) The method of claim 12, further comprising generating neutrons with the neutron source. ### Claim 17 (depends on 16) The method of claim 16, wherein generating neutrons with the neutron source includes utilizing at least one of a DT generator, a DD generator, a gamma source configured to eject a neutron, an electron accelerator beam, or a Bremsstrahlung converter. ### Claim 18 (depends on 12) The method of claim 12, wherein measuring the first response and the second response each include utilizing an active neutron detector. ### Claim 19 (depends on 12) The method of claim 12, wherein measuring the first response and the second response each include utilizing a passive neutron detector. ### Claim 20 (depends on 12) The method of claim 12, wherein measuring the first response and measuring the second response comprises measuring one of the first response and the second response as a positive response and the other of the first response and the second response as a negative response.