{"id":{"repo_id":"vt","oai_identifier":"oai:vtechworks.lib.vt.edu:10919/74618"},"canonical_url":"https://search.dev.ndltd.org/etd/vt/oai:vtechworks.lib.vt.edu:10919/74618","repository":{"repo_id":"vt","name":"Virginia Tech","base_url":"https://vtechworks.lib.vt.edu/oai/request"},"display":{"title":"The Phase Space Time Evolution method applied to multigroup neutron transport","abstract":"The Phase Space Time Evolution (PSTE) method was initially developed for one speed neutrons. This discussion considers the alterations performed in transforming the one speed case to a more general multigroup code. Also the complications which arose in this transformation are discussed. The multigroup formulation of the PSTE method calculates the energy dependent scalar and angular neutron density at very small time increments. In a reactor even slow neutrons travel at relatively high velocities and therefore to keep the distance the particles travel on the order of their mean free path, a small time increment must be used. To illustrate the usefulness of the PSTE method, the time evolution of the neutron density of a nuclear device is modeled in slab geometry and the energy dependent scalar and angular flux is displayed as a function of time and space.","abstract_html":"The Phase Space Time Evolution (PSTE) method was initially developed for one speed neutrons. This discussion considers the alterations performed in transforming the one speed case to a more general multigroup code. Also the complications which arose in this transformation are discussed. The multigroup formulation of the PSTE method calculates the energy dependent scalar and angular neutron density at very small time increments. In a reactor even slow neutrons travel at relatively high velocities and therefore to keep the distance the particles travel on the order of their mean free path, a small time increment must be used. To illustrate the usefulness of the PSTE method, the time evolution of the neutron density of a nuclear device is modeled in slab geometry and the energy dependent scalar and angular flux is displayed as a function of time and space.","abstract_has_math":false,"creators":["Jones, Richard B."],"institution":"Virginia Polytechnic Institute and State University","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":1971,"date_issued":"1971","date_published":"1971","updated_at":"2026-07-22T22:19:01Z","subjects":[],"languages":["en"],"rights":["In Copyright"],"rights_urls":["http://rightsstatements.org/vocab/InC/1.0/"],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/10919/74618","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":["Jones, Richard B."]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2017-01-30T21:03:29Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2017-01-30T21:03:29Z"]},{"key":"dc:date.issued","label":"Date","values":["1971"]},{"key":"dc:publisher","label":"Institution","values":["Virginia Polytechnic Institute and State University"]},{"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 and State University"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language.iso","label":"Language (ISO)","values":["en"]},{"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/10919/74618"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["The Phase Space Time Evolution (PSTE) method was initially developed for one speed neutrons. This discussion considers the alterations performed in transforming the one speed case to a more general multigroup code. Also the complications which arose in this transformation are discussed. The multigroup formulation of the PSTE method calculates the energy dependent scalar and angular neutron density at very small time increments. In a reactor even slow neutrons travel at relatively high velocities and therefore to keep the distance the particles travel on the order of their mean free path, a small time increment must be used. To illustrate the usefulness of the PSTE method, the time evolution of the neutron density of a nuclear device is modeled in slab geometry and the energy dependent scalar and angular flux is displayed as a function of time and space."]},{"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":["The Phase Space Time Evolution method applied to multigroup neutron transport"]}]}],"canonical_facts":{"dc:contributor.department":["Nuclear Science and Engineering"],"dc:creator":["Jones, Richard B."],"dc:date.accessioned":["2017-01-30T21:03:29Z"],"dc:date.available":["2017-01-30T21:03:29Z"],"dc:date.issued":["1971"],"dc:description.abstract":["The Phase Space Time Evolution (PSTE) method was initially developed for one speed neutrons. This discussion considers the alterations performed in transforming the one speed case to a more general multigroup code. Also the complications which arose in this transformation are discussed. The multigroup formulation of the PSTE method calculates the energy dependent scalar and angular neutron density at very small time increments. In a reactor even slow neutrons travel at relatively high velocities and therefore to keep the distance the particles travel on the order of their mean free path, a small time increment must be used. To illustrate the usefulness of the PSTE method, the time evolution of the neutron density of a nuclear device is modeled in slab geometry and the energy dependent scalar and angular flux is displayed as a function of time and space."],"dc:description.degree":["Master of Science"],"dc:format.mimetype":["application/pdf"],"dc:identifier.uri":["http://hdl.handle.net/10919/74618"],"dc:language.iso":["en"],"dc:publisher":["Virginia Polytechnic Institute and State University"],"dc:rights":["In Copyright"],"dc:rights.uri":["http://rightsstatements.org/vocab/InC/1.0/"],"dc:title":["The Phase Space Time Evolution method applied to multigroup neutron transport"],"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 and State University"]},"updated_at":"2026-07-22T22:19:01Z"}