Thermal hydraulic analysis of a PWR loaded with annular fuel rods
In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of increasing the power density of a PWR reactor without c...
Saved in:
| Main Authors: | , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2021-07-01
|
| Series: | Brazilian Journal of Radiation Sciences |
| Subjects: | |
| Online Access: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/1336 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| _version_ | 1850104931594272768 |
|---|---|
| author | Wallen Ferreira De Souza Maria Auxiliadora Fortini Veloso Antonella Lombardi Costa Clubia Pereira |
| author_facet | Wallen Ferreira De Souza Maria Auxiliadora Fortini Veloso Antonella Lombardi Costa Clubia Pereira |
| author_sort | Wallen Ferreira De Souza |
| collection | DOAJ |
| description | In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of increasing the power density of a PWR reactor without compromising the safety margins of the installation. The thermal hydraulic conditions were calculated with the aid of the VIPRE subchannel code, which is a widely used tool in the analysis of nuclear reactor cores. STHIRP-1 is a subchannel code that has been developed at the Departamento de Engenharia Nuclear /UFMG. In order to evaluate the capacity of the STHIRP-1 program, mainly in relation to the thermal model, the new fuel concept was analyzed. The results were compared with those performed with the VIPRE code presented in the reference document. |
| format | Article |
| id | doaj-art-f99ff7aedaad47cb8f72d42bc8472f33 |
| institution | DOAJ |
| issn | 2319-0612 |
| language | English |
| publishDate | 2021-07-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| spelling | doaj-art-f99ff7aedaad47cb8f72d42bc8472f332025-08-20T02:39:14ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122021-07-0192B (Suppl.)10.15392/bjrs.v9i2B.13361041Thermal hydraulic analysis of a PWR loaded with annular fuel rodsWallen Ferreira De Souza0Maria Auxiliadora Fortini Veloso1Antonella Lombardi Costa2Clubia Pereira3UFMG- Universidade Federal De Minas GeraisUFMG- Universidade Federal De Minas GeraisUFMG- Universidade Federal De Minas GeraisUFMG- Universidade Federal De Minas GeraisIn 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of increasing the power density of a PWR reactor without compromising the safety margins of the installation. The thermal hydraulic conditions were calculated with the aid of the VIPRE subchannel code, which is a widely used tool in the analysis of nuclear reactor cores. STHIRP-1 is a subchannel code that has been developed at the Departamento de Engenharia Nuclear /UFMG. In order to evaluate the capacity of the STHIRP-1 program, mainly in relation to the thermal model, the new fuel concept was analyzed. The results were compared with those performed with the VIPRE code presented in the reference document.https://bjrs.org.br/revista/index.php/REVISTA/article/view/1336annular fuelsubchannel codesthirpthermal model |
| spellingShingle | Wallen Ferreira De Souza Maria Auxiliadora Fortini Veloso Antonella Lombardi Costa Clubia Pereira Thermal hydraulic analysis of a PWR loaded with annular fuel rods Brazilian Journal of Radiation Sciences annular fuel subchannel code sthirp thermal model |
| title | Thermal hydraulic analysis of a PWR loaded with annular fuel rods |
| title_full | Thermal hydraulic analysis of a PWR loaded with annular fuel rods |
| title_fullStr | Thermal hydraulic analysis of a PWR loaded with annular fuel rods |
| title_full_unstemmed | Thermal hydraulic analysis of a PWR loaded with annular fuel rods |
| title_short | Thermal hydraulic analysis of a PWR loaded with annular fuel rods |
| title_sort | thermal hydraulic analysis of a pwr loaded with annular fuel rods |
| topic | annular fuel subchannel code sthirp thermal model |
| url | https://bjrs.org.br/revista/index.php/REVISTA/article/view/1336 |
| work_keys_str_mv | AT wallenferreiradesouza thermalhydraulicanalysisofapwrloadedwithannularfuelrods AT mariaauxiliadorafortiniveloso thermalhydraulicanalysisofapwrloadedwithannularfuelrods AT antonellalombardicosta thermalhydraulicanalysisofapwrloadedwithannularfuelrods AT clubiapereira thermalhydraulicanalysisofapwrloadedwithannularfuelrods |