Development and validation of transient Thermal-Hydraulic model for SFR steam generators. (January 2023)
- Record Type:
- Journal Article
- Title:
- Development and validation of transient Thermal-Hydraulic model for SFR steam generators. (January 2023)
- Main Title:
- Development and validation of transient Thermal-Hydraulic model for SFR steam generators
- Authors:
- Vikram, G.
Natesan, K.
Rajendrakumar, M.
Pathak, S.P. - Abstract:
- Highlights: A thermal–hydraulic model for an SFR SG is created using the FLOWNEX code. The model uses fixed meshes with regime-specific flow and heat transfer correlations. Steady-state predictions of the model are validated by inter-code comparison. Transient predictions of the model are validated against ETEC and SGTF experiments. Abstract: The steam generator (SG) is an important component in sodium-cooled fast reactors (SFRs). It transfers the heat from sodium systems to the balance of plant (BOP), producing steam for electricity production. Any disturbances originating from the BOP propagate to the nuclear systems through SG. Hence, it is especially important to model and predict the thermal–hydraulic behavior of SG during such transients. Towards this, a thermal–hydraulic model of SG of a typical medium-sized SFR has been developed using general-purpose system simulation code – FLOWNEX. Usually, the moving boundary method is used to model SGs as it involves phase change and multiple heat transfer regimes. However, in the current model, the fixed mesh approach, generally used for modeling pipelines, single-phase heat exchangers, etc. in plant dynamic codes, has been used to model SGs. In this paper, the modeling details and the solution procedures used in the FLOWNEX are discussed in detail. The steady-state results of the model developed have been compared with the results from in-house code DESOPT. The results were in good agreement at various power levels as well asHighlights: A thermal–hydraulic model for an SFR SG is created using the FLOWNEX code. The model uses fixed meshes with regime-specific flow and heat transfer correlations. Steady-state predictions of the model are validated by inter-code comparison. Transient predictions of the model are validated against ETEC and SGTF experiments. Abstract: The steam generator (SG) is an important component in sodium-cooled fast reactors (SFRs). It transfers the heat from sodium systems to the balance of plant (BOP), producing steam for electricity production. Any disturbances originating from the BOP propagate to the nuclear systems through SG. Hence, it is especially important to model and predict the thermal–hydraulic behavior of SG during such transients. Towards this, a thermal–hydraulic model of SG of a typical medium-sized SFR has been developed using general-purpose system simulation code – FLOWNEX. Usually, the moving boundary method is used to model SGs as it involves phase change and multiple heat transfer regimes. However, in the current model, the fixed mesh approach, generally used for modeling pipelines, single-phase heat exchangers, etc. in plant dynamic codes, has been used to model SGs. In this paper, the modeling details and the solution procedures used in the FLOWNEX are discussed in detail. The steady-state results of the model developed have been compared with the results from in-house code DESOPT. The results were in good agreement at various power levels as well as in off-design conditions. The transient performance of the model has been validated against an in-house experiment carried out in Steam Generator Test Facility (SGTF), IGCAR, India, and a steam generator shutdown experiment carried out in Energy Technology Engineering Center (ETEC), Santa Susana Field Laboratory (SSFL), USA. The transient results were also in good agreement, thereby increasing the confidence level of the predictions. The model developed will be integrated to plant dynamic codes containing other system models and will be used to carry out system-level simulations in the future. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 180(2023)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 180(2023)
- Issue Display:
- Volume 180, Issue 2023 (2023)
- Year:
- 2023
- Volume:
- 180
- Issue:
- 2023
- Issue Sort Value:
- 2023-0180-2023-0000
- Page Start:
- Page End:
- Publication Date:
- 2023-01
- Subjects:
- Sodium-cooled fast reactor -- Once-through steam generator -- Thermal hydraulic model -- Control volume method -- Transient analysis -- FLOWNEX
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2022.109490 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
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