Nuclear data processing for crosssections generation for fusion-fission, ads, and iv generation reactors utilization
| dc.creator | Carlos Eduardo Velasquez Cabrera | |
| dc.creator | Lorena Cunha Fernandes | |
| dc.creator | Maria Auxiliadora f. Veloso | |
| dc.creator | Antonella l. Costa | |
| dc.creator | Claubia Pereira | |
| dc.date.accessioned | 2025-02-14T19:53:38Z | |
| dc.date.accessioned | 2025-09-09T01:21:29Z | |
| dc.date.available | 2025-02-14T19:53:38Z | |
| dc.date.issued | 2017 | |
| dc.format.mimetype | ||
| dc.identifier.uri | https://hdl.handle.net/1843/80097 | |
| dc.language | eng | |
| dc.publisher | Universidade Federal de Minas Gerais | |
| dc.relation.ispartof | International Nuclear Atlantic Conference | |
| dc.rights | Acesso Aberto | |
| dc.subject | Reatores nucleares | |
| dc.subject | Nêutrons | |
| dc.subject | Fusão | |
| dc.subject.other | Nuclear reactors | |
| dc.subject.other | Neutrons | |
| dc.subject.other | Fusion | |
| dc.title | Nuclear data processing for crosssections generation for fusion-fission, ads, and iv generation reactors utilization | |
| dc.type | Artigo de evento | |
| local.citation.epage | 11 | |
| local.citation.spage | 1 | |
| local.description.resumo | One of the mains topics about nuclear reactors is the microscopic cross section for incident neutrons. Therefore, in this work, it is evaluated the microscopic and macroscopic cross section for a nuclide and a material. One of the nuclides microscopic cross-section studied is the 56Fe which is the highest compound from the material macroscopic cross section studied SS316. On the other hand, it was studied the microscopic cross section of the 242Pu which is one of the nuclides that composes the nuclear fuel. The nuclear fuel chosen is a spent fuel reprocessed by UREX+ technique and spiked with thorium with 20% of fissile material. Therefore it was studied the macroscopic cross section from this nuclear fuel. Both of them were compared by using three different ways to reprocess the nuclides, one for LWR, another for ADS and the last one for Fusion reactors. The library used was JEFF-3.2 recommend for the reactors studied. The comparison was made at 1200 K for the nuclear fuel and 700K for the SS316.The results present differences due to the energy discretization, the number of groups chosen for each reactor and some nuclear reactions taken into consideration according to the neutron spectrum for each reactor. The nuclides were processed by NJOY99.364 and plotted with MCNP-Vised. | |
| local.identifier.orcid | https://orcid.org/0000-0002-2960-3150 | |
| local.identifier.orcid | https://orcid.org/0000-0001-8618-8195 | |
| local.identifier.orcid | https://orcid.org/0000-0002-2445-3800 | |
| local.identifier.orcid | https://orcid.org/0000-0001-5999-9961 | |
| local.publisher.country | Brasil | |
| local.publisher.department | ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR | |
| local.publisher.initials | UFMG | |
| local.url.externa | https://inis.iaea.org/records/tjm1e-1xm33 |