Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power
This paper gives an account of the development and validation of an up-to-date coupled neutronic/thermal-hydraulic model for the Swedish Forsmark boiling water reactor. The model will be used for analyses of the consequences of the planned power uprate from 2928 MWth to 3253 MWth. At first, the dev...
| Main Authors: | , |
|---|---|
| Format: | Conference or Workshop Item |
| Language: | English |
| Published: |
2014
|
| Subjects: | |
| Online Access: | https://repository.ugm.ac.id/275200/1/NUTHOS10_paper%20lengkap.pdf |
| _version_ | 1797036930214395904 |
|---|---|
| author | Agung, Alexander Bánáti, József |
| author_facet | Agung, Alexander Bánáti, József |
| author_sort | Agung, Alexander |
| collection | UGM |
| description | This paper gives an account of the development and validation of an up-to-date coupled neutronic/thermal-hydraulic model for the Swedish Forsmark boiling water reactor. The model will be used for analyses of the consequences of the planned power uprate from 2928 MWth to 3253 MWth.
At first, the development of the PARCS and RELAP5 models are presented. On the neutronic side, cross-sections data was generated, allowing feeding PARCS with realistic data. This step was performed by converting the library data file from the power plant using the in-house cross-section interface code. The dependence of the material properties on history effects, burnup, and instantaneous conditions was accounted for, and the full heterogeneity of the core was thus taken into account. Each of the 676 fuel assemblies was modeled individually, while the 161 control rods were grouped into 6 different types. On the thermal-hydraulic side, the model consists of a model for the feedwater system, a model for the reactor vessel that include a model for the core channels, and a model for each of the four steam lines. The fuel assemblies were modeled as twelve flow channels in the core region. The coupling between the two codes is touched upon, with emphasis on the mapping between the hydrodynamic/heat structures and the neutronic nodes.
The validation efforts were focusing on benchmarking the code capabilities against measured plant data, both under steady-state and transient conditions. The PARCS standalone model was validated against traversing in-core probe (TIP) measurements, taken at different burnup level with operating power varies from 108% (nominal level) to 120% (uprated level). The coupled PARCS/RELAP5 model was validated against an operational transient. For this validation task, the transient chosen was a turbine trip test, which was performed on May 6, 2013.
Comparisons between calculated and measured parameters demonstrate that the coupled model was able to correctly represent the steady-state conditions of the plant. The validation of the coupled model against measured transient plant data was then performed. It has been demonstrated that the coupled model is able to capture the main features of the transient with a sufficient level of accuracy. |
| first_indexed | 2024-03-13T23:54:37Z |
| format | Conference or Workshop Item |
| id | oai:generic.eprints.org:275200 |
| institution | Universiti Gadjah Mada |
| language | English |
| last_indexed | 2024-03-13T23:54:37Z |
| publishDate | 2014 |
| record_format | dspace |
| spelling | oai:generic.eprints.org:2752002019-07-26T06:56:11Z https://repository.ugm.ac.id/275200/ Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power Agung, Alexander Bánáti, József Nuclear Engineering This paper gives an account of the development and validation of an up-to-date coupled neutronic/thermal-hydraulic model for the Swedish Forsmark boiling water reactor. The model will be used for analyses of the consequences of the planned power uprate from 2928 MWth to 3253 MWth. At first, the development of the PARCS and RELAP5 models are presented. On the neutronic side, cross-sections data was generated, allowing feeding PARCS with realistic data. This step was performed by converting the library data file from the power plant using the in-house cross-section interface code. The dependence of the material properties on history effects, burnup, and instantaneous conditions was accounted for, and the full heterogeneity of the core was thus taken into account. Each of the 676 fuel assemblies was modeled individually, while the 161 control rods were grouped into 6 different types. On the thermal-hydraulic side, the model consists of a model for the feedwater system, a model for the reactor vessel that include a model for the core channels, and a model for each of the four steam lines. The fuel assemblies were modeled as twelve flow channels in the core region. The coupling between the two codes is touched upon, with emphasis on the mapping between the hydrodynamic/heat structures and the neutronic nodes. The validation efforts were focusing on benchmarking the code capabilities against measured plant data, both under steady-state and transient conditions. The PARCS standalone model was validated against traversing in-core probe (TIP) measurements, taken at different burnup level with operating power varies from 108% (nominal level) to 120% (uprated level). The coupled PARCS/RELAP5 model was validated against an operational transient. For this validation task, the transient chosen was a turbine trip test, which was performed on May 6, 2013. Comparisons between calculated and measured parameters demonstrate that the coupled model was able to correctly represent the steady-state conditions of the plant. The validation of the coupled model against measured transient plant data was then performed. It has been demonstrated that the coupled model is able to capture the main features of the transient with a sufficient level of accuracy. 2014 Conference or Workshop Item PeerReviewed application/pdf en https://repository.ugm.ac.id/275200/1/NUTHOS10_paper%20lengkap.pdf Agung, Alexander and Bánáti, József (2014) Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power. In: The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), 14-18 Desember 2014, Okinawa, Japan. |
| spellingShingle | Nuclear Engineering Agung, Alexander Bánáti, József Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title | Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title_full | Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title_fullStr | Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title_full_unstemmed | Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title_short | Development and Validation of Coupled PARCS/RELAP5 Model for Forsmark NPP at Uprated Power |
| title_sort | development and validation of coupled parcs relap5 model for forsmark npp at uprated power |
| topic | Nuclear Engineering |
| url | https://repository.ugm.ac.id/275200/1/NUTHOS10_paper%20lengkap.pdf |
| work_keys_str_mv | AT agungalexander developmentandvalidationofcoupledparcsrelap5modelforforsmarknppatupratedpower AT banatijozsef developmentandvalidationofcoupledparcsrelap5modelforforsmarknppatupratedpower |