Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC. (3rd May 2017)
- Record Type:
- Journal Article
- Title:
- Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC. (3rd May 2017)
- Main Title:
- Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC
- Authors:
- Liu, Li
Guo, Yong
Chan, Vincent
Mao, Shifeng
Wang, Yifeng
Pan, Chengkang
Luo, Zhengping
Zhao, Hailin
Ye, Minyou - Abstract:
- Abstract: The confidence in ramp up scenario design of the China fusion engineering test reactor (CFETR) can be significantly enhanced using validated transport models to predict the current profile and temperature profile. In the tokamak simulation code (TSC), two semi-empirical energy transport models (the Coppi-Tang (CT) and BGB model) and three theory-based models (the GLF23, MMM95 and CDBM model) are investigated on the CFETR relevant ramp up discharges, including three DIII-D ITER-like ramp up discharges and one EAST ohmic discharge. For the DIII-D discharges, all the transport models yield dynamic ℓ i within ± 0.15 deviations except for some time points where the experimental fluctuation is very strong. All the models agree with the experimental β p except that the CT model strongly overestimates β p in the first half of ramp up phase. When applying the CT, CDBM and GLF23 model to estimate the internal flux, they show maximum deviations of more than 10% because of inaccuracies in the temperature profile predictions, while the BGB model performs best on the internal flux. Although all the models fall short in reproducing the dynamic ℓ i evolution for the EAST tokamak, the result of the BGB model is the closest to the experimental ℓ i . Based on these comparisons, we conclude that the BGB model is the most consistent among these models for simulating CFETR ohmic ramp-up. The CT model with improvement for better simulation of the temperature profiles in the first half ofAbstract: The confidence in ramp up scenario design of the China fusion engineering test reactor (CFETR) can be significantly enhanced using validated transport models to predict the current profile and temperature profile. In the tokamak simulation code (TSC), two semi-empirical energy transport models (the Coppi-Tang (CT) and BGB model) and three theory-based models (the GLF23, MMM95 and CDBM model) are investigated on the CFETR relevant ramp up discharges, including three DIII-D ITER-like ramp up discharges and one EAST ohmic discharge. For the DIII-D discharges, all the transport models yield dynamic ℓ i within ± 0.15 deviations except for some time points where the experimental fluctuation is very strong. All the models agree with the experimental β p except that the CT model strongly overestimates β p in the first half of ramp up phase. When applying the CT, CDBM and GLF23 model to estimate the internal flux, they show maximum deviations of more than 10% because of inaccuracies in the temperature profile predictions, while the BGB model performs best on the internal flux. Although all the models fall short in reproducing the dynamic ℓ i evolution for the EAST tokamak, the result of the BGB model is the closest to the experimental ℓ i . Based on these comparisons, we conclude that the BGB model is the most consistent among these models for simulating CFETR ohmic ramp-up. The CT model with improvement for better simulation of the temperature profiles in the first half of ramp up phase will also be attractive. For the MMM95, GLF23 and CDBM model, better prediction of the edge temperature will improve the confidence for CFETR L-mode simulation. Conclusive validation of any transport model will require extensive future investigation covering a larger variety discharges. … (more)
- Is Part Of:
- Nuclear fusion. Volume 57:Number 6(2017:Jun.)
- Journal:
- Nuclear fusion
- Issue:
- Volume 57:Number 6(2017:Jun.)
- Issue Display:
- Volume 57, Issue 6 (2017)
- Year:
- 2017
- Volume:
- 57
- Issue:
- 6
- Issue Sort Value:
- 2017-0057-0006-0000
- Page Start:
- Page End:
- Publication Date:
- 2017-05-03
- Subjects:
- transport models -- tokamak ramp up -- tokamak simulation code (TSC)
Nuclear fusion -- Periodicals
621.48405 - Journal URLs:
- http://www.iop.org/EJ/journal/0029-5515 ↗
http://iopscience.iop.org/0029-5515/ ↗
http://ioppublishing.org/ ↗ - DOI:
- 10.1088/1741-4326/aa6b7f ↗
- Languages:
- English
- ISSNs:
- 0029-5515
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - BLDSS-3PM
British Library STI - ELD Digital store - Ingest File:
- 14051.xml