{"id":{"repo_id":"missouri","oai_identifier":"oai:mospace.umsystem.edu:10355/45661"},"canonical_url":"https://search.dev.ndltd.org/etd/missouri/oai:mospace.umsystem.edu:10355/45661","repository":{"repo_id":"missouri","name":"University of Missouri","base_url":"https://mospace.umsystem.edu/oai/request"},"display":{"title":"Maximum hypothetical accident analysis for HEU to LEU fuel conversion at the University of Missouri Research Reactor","abstract":"As a part of the Global Threat Reduction Initiative (GTRI) and the Reduced Enrichment for Research and Test Reactors (RERTR) programs, the University of Missouri Research Reactor (MURR) intends to convert from 93% highly-enriched uranium (HEU) aluminide dispersion fuel to 19.75% low-enrichment uranium (LEU) U-Mo monolithic fuel. Under chapter 13 of NUREG-1573, MURR must perform several safety analyses, one of which was the maximum hypothetical accident (MHA) analysis. For the 10-minute dose to workers in containment, a committed effective dose equivalent (CEDE) to the thyroid from the radioiodines was 0.889 mrem. To calculate the total effective dose equivalent (TEDE), two different sets of derived air concentrations (DACs) were used. Using the 10 CFR 20 default DAC for four nuclides with unlisted DACs, the TEDE was 1403 mrem. Using the pre-2007 version of 10 CFR 835 DACs for three of the unlisted radionuclides, the TEDE was 403 mrem. For the 16.5-hour dose to a member of the public beyond the exclusionary boundary area (EBA) of MURR, the CEDE to the thyroid was 0 mrem, the TEDE using the 10 CFR 20 default DAC was 8.58 mrem, and the TEDE using the pre-2007 version of 10 CFR 835 DACs was 2.45 mrem.","abstract_html":"As a part of the Global Threat Reduction Initiative (GTRI) and the Reduced Enrichment for Research and Test Reactors (RERTR) programs, the University of Missouri Research Reactor (MURR) intends to convert from 93% highly-enriched uranium (HEU) aluminide dispersion fuel to 19.75% low-enrichment uranium (LEU) U-Mo monolithic fuel. Under chapter 13 of NUREG-1573, MURR must perform several safety analyses, one of which was the maximum hypothetical accident (MHA) analysis. For the 10-minute dose to workers in containment, a committed effective dose equivalent (CEDE) to the thyroid from the radioiodines was 0.889 mrem. To calculate the total effective dose equivalent (TEDE), two different sets of derived air concentrations (DACs) were used. Using the 10 CFR 20 default DAC for four nuclides with unlisted DACs, the TEDE was 1403 mrem. Using the pre-2007 version of 10 CFR 835 DACs for three of the unlisted radionuclides, the TEDE was 403 mrem. For the 16.5-hour dose to a member of the public beyond the exclusionary boundary area (EBA) of MURR, the CEDE to the thyroid was 0 mrem, the TEDE using the 10 CFR 20 default DAC was 8.58 mrem, and the TEDE using the pre-2007 version of 10 CFR 835 DACs was 2.45 mrem.","abstract_has_math":false,"creators":["Cowherd, Wilson"],"institution":"University of Missouri--Columbia","degree_name":"M.S.","degree_level":"Masters","degree_discipline":"Nuclear engineering (MU)","degree_department":null,"school":null,"contributors":[],"advisors":["Miller, William Hughes, 1941-"],"committee_chairs":[],"committee_members":[],"year":2014,"date_issued":"2014","date_published":"2014","updated_at":"2026-07-24T03:09:39Z","subjects":[],"languages":["eng","English"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10355/45661","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Miller, William Hughes, 1941-"]},{"key":"dc:creator","label":"Author","values":["Cowherd, Wilson"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2015-05-28T19:18:54Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2015-05-28T19:18:54Z"]},{"key":"dc:date.issued","label":"Date","values":["2014"]},{"key":"dc:publisher","label":"Institution","values":["University of Missouri--Columbia"]},{"key":"dc:type","label":"Dc Type","values":["Thesis"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear engineering (MU)"]},{"key":"thesis:degree_level","label":"Degree Level","values":["Masters"]},{"key":"thesis:degree_name","label":"Degree Name","values":["M.S."]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["University of Missouri--Columbia"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["English"]},{"key":"dc:language.iso","label":"Language (ISO)","values":["eng"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier.uri","label":"Identifier URI","values":["https://hdl.handle.net/10355/45661"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["As a part of the Global Threat Reduction Initiative (GTRI) and the Reduced Enrichment for Research and Test Reactors (RERTR) programs, the University of Missouri Research Reactor (MURR) intends to convert from 93% highly-enriched uranium (HEU) aluminide dispersion fuel to 19.75% low-enrichment uranium (LEU) U-Mo monolithic fuel. Under chapter 13 of NUREG-1573, MURR must perform several safety analyses, one of which was the maximum hypothetical accident (MHA) analysis. For the 10-minute dose to workers in containment, a committed effective dose equivalent (CEDE) to the thyroid from the radioiodines was 0.889 mrem. To calculate the total effective dose equivalent (TEDE), two different sets of derived air concentrations (DACs) were used. Using the 10 CFR 20 default DAC for four nuclides with unlisted DACs, the TEDE was 1403 mrem. Using the pre-2007 version of 10 CFR 835 DACs for three of the unlisted radionuclides, the TEDE was 403 mrem. For the 16.5-hour dose to a member of the public beyond the exclusionary boundary area (EBA) of MURR, the CEDE to the thyroid was 0 mrem, the TEDE using the 10 CFR 20 default DAC was 8.58 mrem, and the TEDE using the pre-2007 version of 10 CFR 835 DACs was 2.45 mrem."]},{"key":"dc:source","label":"Dc Source","values":["Submitted by University of Missouri--Columbia Graduate School."]},{"key":"dc:title","label":"Title","values":["Maximum hypothetical accident analysis for HEU to LEU fuel conversion at the University of Missouri Research Reactor"]}]}],"canonical_facts":{"dc:contributor.advisor":["Miller, William Hughes, 1941-"],"dc:creator":["Cowherd, Wilson"],"dc:date.accessioned":["2015-05-28T19:18:54Z"],"dc:date.available":["2015-05-28T19:18:54Z"],"dc:date.issued":["2014"],"dc:description.abstract":["As a part of the Global Threat Reduction Initiative (GTRI) and the Reduced Enrichment for Research and Test Reactors (RERTR) programs, the University of Missouri Research Reactor (MURR) intends to convert from 93% highly-enriched uranium (HEU) aluminide dispersion fuel to 19.75% low-enrichment uranium (LEU) U-Mo monolithic fuel. Under chapter 13 of NUREG-1573, MURR must perform several safety analyses, one of which was the maximum hypothetical accident (MHA) analysis. For the 10-minute dose to workers in containment, a committed effective dose equivalent (CEDE) to the thyroid from the radioiodines was 0.889 mrem. To calculate the total effective dose equivalent (TEDE), two different sets of derived air concentrations (DACs) were used. Using the 10 CFR 20 default DAC for four nuclides with unlisted DACs, the TEDE was 1403 mrem. Using the pre-2007 version of 10 CFR 835 DACs for three of the unlisted radionuclides, the TEDE was 403 mrem. For the 16.5-hour dose to a member of the public beyond the exclusionary boundary area (EBA) of MURR, the CEDE to the thyroid was 0 mrem, the TEDE using the 10 CFR 20 default DAC was 8.58 mrem, and the TEDE using the pre-2007 version of 10 CFR 835 DACs was 2.45 mrem."],"dc:identifier.uri":["https://hdl.handle.net/10355/45661"],"dc:language":["English"],"dc:language.iso":["eng"],"dc:publisher":["University of Missouri--Columbia"],"dc:source":["Submitted by University of Missouri--Columbia Graduate School."],"dc:title":["Maximum hypothetical accident analysis for HEU to LEU fuel conversion at the University of Missouri Research Reactor"],"dc:type":["Thesis"],"thesis:degree_discipline":["Nuclear engineering (MU)"],"thesis:degree_level":["Masters"],"thesis:degree_name":["M.S."],"thesis:institution_name":["University of Missouri--Columbia"]},"updated_at":"2026-07-24T03:09:39Z"}