The Switchable Radioisotope Generator utilizes alpha-induced reactions to produce a combination of photons, neutrons, and protons with varying fluxes dependent on target materials and source geometry. The activity/strength of the secondary radiation is further controlled by manipulating the number of alpha particles that can interact with the target material(s). Analytical equations were solved to confirm secondary radiation production from target materials using average cross sections from TENDL data. TENDL and JENDL data was confirmed by analytically solving for the total alpha-induced cross sections. This information was used to produce the provisional and utility Patent No: US20190013109A1. TENDL data was then used to write cross sections within NJOY, including the ACER module. The completed cross sections were arranged in MCNP 6.1.1, such that alpha interactions may be simulated. Angular-energy dependence of secondary neutrons from 9Be(α, n)12C were chosen for simulation study, as this reaction would be validated later on experimentally due to having the highest reaction rate.
The experimental results confirmed data obtained through simulation studies with differences between the two justified. Secondary neutrons produced were coded in SDEF within MCNP 6.1.1 for neutron radiography to allow for defect detection within canister and cask materials. PGNAA was simulated in MCNP with SNM and harmful chemicals using secondary neutrons from the SRG as another application study. The SRG was then proven to detect microstructure defects in cask and canister materials and positively identify SNM and chemical agents using PGNAA”--Abstract, page iii.
","abstract_html":"<p>The Switchable Radioisotope Generator utilizes alpha-induced reactions to produce a combination of photons, neutrons, and protons with varying fluxes dependent on target materials and source geometry. The activity/strength of the secondary radiation is further controlled by manipulating the number of alpha particles that can interact with the target material(s). Analytical equations were solved to confirm secondary radiation production from target materials using average cross sections from TENDL data. TENDL and JENDL data was confirmed by analytically solving for the total alpha-induced cross sections. This information was used to produce the provisional and utility Patent No: US20190013109A1. TENDL data was then used to write cross sections within NJOY, including the ACER module. The completed cross sections were arranged in MCNP 6.1.1, such that alpha interactions may be simulated. Angular-energy dependence of secondary neutrons from <sup>9</sup>Be(α, n)<sup>12</sup>C were chosen for simulation study, as this reaction would be validated later on experimentally due to having the highest reaction rate.</p><p>The experimental results confirmed data obtained through simulation studies with differences between the two justified. Secondary neutrons produced were coded in SDEF within MCNP 6.1.1 for neutron radiography to allow for defect detection within canister and cask materials. PGNAA was simulated in MCNP with SNM and harmful chemicals using secondary neutrons from the SRG as another application study. The SRG was then proven to detect microstructure defects in cask and canister materials and positively identify SNM and chemical agents using PGNAA”--Abstract, page iii.</p>","abstract_has_math":false,"creators":["Paaren, Kyle Mitchell"],"institution":"Missouri University of Science and Technology","degree_name":"Ph. D. in Nuclear Engineering","degree_level":null,"degree_discipline":null,"degree_department":null,"school":null,"contributors":[],"advisors":[],"committee_chairs":[],"committee_members":[],"year":null,"date_issued":"","date_published":null,"updated_at":"2026-07-24T03:18:09Z","subjects":["Active Interrogation","CNR","Cross section","MCNP","NJOY","TENDL","Nuclear","Nuclear Engineering"],"languages":[],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://scholarsmine.mst.edu/doctoral_dissertations/3107","outbound_label":"Repository record","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:creator","label":"Author","values":["Paaren, Kyle Mitchell"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:type","label":"Dc Type","values":["Dissertation - Open Access"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph. D. in Nuclear Engineering"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["Missouri University of Science and Technology"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Active Interrogation","CNR","Cross section","MCNP","NJOY","TENDL","Nuclear","Nuclear Engineering"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://scholarsmine.mst.edu/doctoral_dissertations/3107"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["The Switchable Radioisotope Generator utilizes alpha-induced reactions to produce a combination of photons, neutrons, and protons with varying fluxes dependent on target materials and source geometry. The activity/strength of the secondary radiation is further controlled by manipulating the number of alpha particles that can interact with the target material(s). Analytical equations were solved to confirm secondary radiation production from target materials using average cross sections from TENDL data. TENDL and JENDL data was confirmed by analytically solving for the total alpha-induced cross sections. This information was used to produce the provisional and utility Patent No: US20190013109A1. TENDL data was then used to write cross sections within NJOY, including the ACER module. The completed cross sections were arranged in MCNP 6.1.1, such that alpha interactions may be simulated. Angular-energy dependence of secondary neutrons from 9Be(α, n)12C were chosen for simulation study, as this reaction would be validated later on experimentally due to having the highest reaction rate.
The experimental results confirmed data obtained through simulation studies with differences between the two justified. Secondary neutrons produced were coded in SDEF within MCNP 6.1.1 for neutron radiography to allow for defect detection within canister and cask materials. PGNAA was simulated in MCNP with SNM and harmful chemicals using secondary neutrons from the SRG as another application study. The SRG was then proven to detect microstructure defects in cask and canister materials and positively identify SNM and chemical agents using PGNAA”--Abstract, page iii.
"]},{"key":"dc:title","label":"Title","values":["Development of a switchable radioisotope generator"]}]}],"canonical_facts":{"dc:creator":["Paaren, Kyle Mitchell"],"dc:description.abstract":["The Switchable Radioisotope Generator utilizes alpha-induced reactions to produce a combination of photons, neutrons, and protons with varying fluxes dependent on target materials and source geometry. The activity/strength of the secondary radiation is further controlled by manipulating the number of alpha particles that can interact with the target material(s). Analytical equations were solved to confirm secondary radiation production from target materials using average cross sections from TENDL data. TENDL and JENDL data was confirmed by analytically solving for the total alpha-induced cross sections. This information was used to produce the provisional and utility Patent No: US20190013109A1. TENDL data was then used to write cross sections within NJOY, including the ACER module. The completed cross sections were arranged in MCNP 6.1.1, such that alpha interactions may be simulated. Angular-energy dependence of secondary neutrons from 9Be(α, n)12C were chosen for simulation study, as this reaction would be validated later on experimentally due to having the highest reaction rate.
The experimental results confirmed data obtained through simulation studies with differences between the two justified. Secondary neutrons produced were coded in SDEF within MCNP 6.1.1 for neutron radiography to allow for defect detection within canister and cask materials. PGNAA was simulated in MCNP with SNM and harmful chemicals using secondary neutrons from the SRG as another application study. The SRG was then proven to detect microstructure defects in cask and canister materials and positively identify SNM and chemical agents using PGNAA”--Abstract, page iii.
"],"dc:identifier":["https://scholarsmine.mst.edu/doctoral_dissertations/3107"],"dc:subject":["Active Interrogation","CNR","Cross section","MCNP","NJOY","TENDL","Nuclear","Nuclear Engineering"],"dc:title":["Development of a switchable radioisotope generator"],"dc:type":["Dissertation - Open Access"],"thesis:degree_name":["Ph. D. in Nuclear Engineering"],"thesis:institution_name":["Missouri University of Science and Technology"]},"updated_at":"2026-07-24T03:18:09Z"}