{"id":{"repo_id":"vt","oai_identifier":"oai:vtechworks.lib.vt.edu:10919/70473"},"canonical_url":"https://search.dev.ndltd.org/etd/vt/oai:vtechworks.lib.vt.edu:10919/70473","repository":{"repo_id":"vt","name":"Virginia Tech","base_url":"https://vtechworks.lib.vt.edu/oai/request"},"display":{"title":"An air sampling system to estimate concentrations of argon-41 in the V.P.I. physics building during reactor operation","abstract":"A gamma scintillation spectrometer was assembled. and calibrated in a low background radiation area to analyze air samples. Air samples were taken from different locations in the physics building during reactor operation to determine the concentrations of A⁴¹ released to the surroundings of the building during reactor operation. The samples were collected in a one gallon polyethylene bottle with a 3 ¾” x 3 ¾” cylindrical well sealed in the bottom. The air samples were taken to the counting area and the sampling bottle placed on the detector, a 3” x 3\" cylindrical NaI(TI) crystal which fitted into the well. The pulses from the detector were fed te a multi-channel analyzer. From the number of pulses per unit time under the photo-peak, the concentration of A⁴¹ for each location was determined. Samples were analyzed for 4, 7, and 10 kw from which a linear extrapolation was made to estimate the concentrations of A⁴¹ in these locations if higher power operation is authorized.","abstract_html":"A gamma scintillation spectrometer was assembled. and calibrated in a low background radiation area to analyze air samples. Air samples were taken from different locations in the physics building during reactor operation to determine the concentrations of A⁴¹ released to the surroundings of the building during reactor operation. The samples were collected in a one gallon polyethylene bottle with a 3 ¾” x 3 ¾” cylindrical well sealed in the bottom. The air samples were taken to the counting area and the sampling bottle placed on the detector, a 3” x 3" cylindrical NaI(TI) crystal which fitted into the well. The pulses from the detector were fed te a multi-channel analyzer. From the number of pulses per unit time under the photo-peak, the concentration of A⁴¹ for each location was determined. Samples were analyzed for 4, 7, and 10 kw from which a linear extrapolation was made to estimate the concentrations of A⁴¹ in these locations if higher power operation is authorized.","abstract_has_math":false,"creators":["Putney, Irvin Turner"],"institution":"Virginia Polytechnic Institute","degree_name":"Master of Science","degree_level":"masters","degree_discipline":"Nuclear Science and Engineering","degree_department":"Nuclear Science and Engineering","school":null,"contributors":[],"advisors":[],"committee_chairs":[],"committee_members":[],"year":1963,"date_issued":"1963","date_published":"1963","updated_at":"2026-07-22T22:20:35Z","subjects":["Virginia Polytechnic Institute. -- Equipment and supplies"],"languages":["en_US"],"rights":["In Copyright"],"rights_urls":["http://rightsstatements.org/vocab/InC/1.0/"],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/10919/70473","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.department","label":"Department","values":["Nuclear Science and Engineering"]},{"key":"dc:creator","label":"Author","values":["Putney, Irvin Turner"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2016-04-21T15:34:37Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2016-04-21T15:34:37Z"]},{"key":"dc:date.issued","label":"Date","values":["1963"]},{"key":"dc:publisher","label":"Institution","values":["Virginia Polytechnic Institute"]},{"key":"dc:type","label":"Dc Type","values":["Thesis"]},{"key":"dc:type.dcmitype","label":"Dc Type Dcmitype","values":["Text"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear Science and Engineering"]},{"key":"thesis:degree_level","label":"Degree Level","values":["masters"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Master of Science"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["Virginia Polytechnic Institute"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Virginia Polytechnic Institute. -- Equipment and supplies"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language.iso","label":"Language (ISO)","values":["en_US"]},{"key":"dc:rights","label":"Dc Rights","values":["In Copyright"]},{"key":"dc:rights.uri","label":"Rights URI","values":["http://rightsstatements.org/vocab/InC/1.0/"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier.uri","label":"Identifier URI","values":["http://hdl.handle.net/10919/70473"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["A gamma scintillation spectrometer was assembled. and calibrated in a low background radiation area to analyze air samples. Air samples were taken from different locations in the physics building during reactor operation to determine the concentrations of A⁴¹ released to the surroundings of the building during reactor operation. The samples were collected in a one gallon polyethylene bottle with a 3 ¾” x 3 ¾” cylindrical well sealed in the bottom. The air samples were taken to the counting area and the sampling bottle placed on the detector, a 3” x 3\" cylindrical NaI(TI) crystal which fitted into the well. The pulses from the detector were fed te a multi-channel analyzer. From the number of pulses per unit time under the photo-peak, the concentration of A⁴¹ for each location was determined. Samples were analyzed for 4, 7, and 10 kw from which a linear extrapolation was made to estimate the concentrations of A⁴¹ in these locations if higher power operation is authorized."]},{"key":"dc:description.degree","label":"Dc Description Degree","values":["Master of Science"]},{"key":"dc:format.mimetype","label":"Dc Format Mimetype","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["An air sampling system to estimate concentrations of argon-41 in the V.P.I. physics building during reactor operation"]}]}],"canonical_facts":{"dc:contributor.department":["Nuclear Science and Engineering"],"dc:creator":["Putney, Irvin Turner"],"dc:date.accessioned":["2016-04-21T15:34:37Z"],"dc:date.available":["2016-04-21T15:34:37Z"],"dc:date.issued":["1963"],"dc:description.abstract":["A gamma scintillation spectrometer was assembled. and calibrated in a low background radiation area to analyze air samples. Air samples were taken from different locations in the physics building during reactor operation to determine the concentrations of A⁴¹ released to the surroundings of the building during reactor operation. The samples were collected in a one gallon polyethylene bottle with a 3 ¾” x 3 ¾” cylindrical well sealed in the bottom. The air samples were taken to the counting area and the sampling bottle placed on the detector, a 3” x 3\" cylindrical NaI(TI) crystal which fitted into the well. The pulses from the detector were fed te a multi-channel analyzer. From the number of pulses per unit time under the photo-peak, the concentration of A⁴¹ for each location was determined. Samples were analyzed for 4, 7, and 10 kw from which a linear extrapolation was made to estimate the concentrations of A⁴¹ in these locations if higher power operation is authorized."],"dc:description.degree":["Master of Science"],"dc:format.mimetype":["application/pdf"],"dc:identifier.uri":["http://hdl.handle.net/10919/70473"],"dc:language.iso":["en_US"],"dc:publisher":["Virginia Polytechnic Institute"],"dc:rights":["In Copyright"],"dc:rights.uri":["http://rightsstatements.org/vocab/InC/1.0/"],"dc:subject":["Virginia Polytechnic Institute. -- Equipment and supplies"],"dc:title":["An air sampling system to estimate concentrations of argon-41 in the V.P.I. physics building during reactor operation"],"dc:type":["Thesis"],"dc:type.dcmitype":["Text"],"thesis:degree_discipline":["Nuclear Science and Engineering"],"thesis:degree_level":["masters"],"thesis:degree_name":["Master of Science"],"thesis:institution_name":["Virginia Polytechnic Institute"]},"updated_at":"2026-07-22T22:20:35Z"}