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TRANSP[1] is a computer code for analyzing results from Tokamak experiments with the goal of developing fusion energy as a practical, minimally polluting energy source. TRANSP is developed and maintained at Princeton Plasma Physics Laboratory (PPPL) Princeton University Princeton NJ, USA. Development started in the 1970's and TRANSP continues to be extended and widely used to the present.

During the first four decades, TRANSP was the only, and then the primary integrated code used for studing phenomenon within the plasma boundary of tokamak discharges. Integrated means encompassing the complex interactions of diverse physical processes. It is used to compute properties which cannot be measured directly, such as the radial transport of plasma species, energy, toroidal momentum, and angular momentum. It computes the effects of actuators used to heat and fuel the plasmas. It simulates parameters that can be compared with measurements to verify the accuracy and credibility of the digital model.

TRANSP has also been used successfully to predict future experiments. One early example is a prediction of fusion reaction rates expected from the future deuterium-tritium experiments in Tokamak Fusion Test Reactor (TFTR) at PPPL.[citation needed] A precursor experiment with deuterium plasma was accurately modeled by TRANSP, and then a mix of deuterium and tritium was substituted into the model. The predicted fusion gain QDT, defined as the ratio of the fusion energy produced to the external heating into the plasma, was 0.32. Later deuterium-tritium experiments in 1993–1996 achieved a maximum QDT of 0.28.[2]

Many publications

[3] [4] [5] [6] [7] [8] [9] [10] [11] [12] [13] [14] [15] [16] [17] 

of results from experiments in the TFTR, JET Joint European Torus, and other tokamaks rely[citation needed] on TRANSP-generated results. TRANSP is also being used to predict results from future experiments in ITER.[citation needed] One early example,[18] supports the prediction of achieving QDT in the range 5–14, and possibly higher.

References

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  1. ^ A.Y. Pankin, et al, TRANSP integrated modeling code for interpretive and predictive analysis of tokamak plasmas 2025 Computer Physics Communications 312 109611
  2. ^ Simulations of deuterium–tritium experiments in TFTR Budny R.V. et al 1992 Nucl. Fusion 32 429 DOI 10.1088/0029-5515/32/3/I07
  3. ^ 'Isotopic mass effects of tritium-fueled high-performance TFTR supershots' R.V. Budny*, E. Fredrickson and C.H. Skinner Nucl. Fusion 65 056005 https://doi.org/10.1088/1741-4326/adbe8
  4. ^ "Alpha heating, isotopic mass, and fast ion effects in deuterium-tritium experiments", R.V. Budny and JET Contributors, Nuclear Fus. (2018) <58> 096011 #9 (Sep) https://doi.org/10.1088/1741-4326/aaca04
  5. ^ "Core fusion power gain and alpha heating in JET, TFTR, and ITER", R.V. Budny, J.G. Cordey and TFTR Team and JET Contributors, Nuclear Fus. (2016) <56> 056002 #5 (May) https://iopscience.iop.org/article/10.1088/0029-5515/56/5/056002 //home/budny/papers/NF/core_q_dt/nf_56_5_056002.pdf
  6. ^ "Benchmarking ICRF full-wave solvers for ITER", R.V. Budny, L. Berry, R. Bilato, P. Bonoli, M. Brambilla, R.J. Dumont, et al., Nuclear Fus. (2012) <52> 023023 Feb https://iopscience.iop.org/article/10.1088/0029-5515/52/2/023023
  7. ^ "Alpha heating in ITER L-mode and H-mode plasmas", R. V. Budny, Nuclear Fus. (2012) <52> 013001 Jan DOI 10.1088/0029-5515/52/1/013001
  8. ^ "Comparisons of predicted plasma performance in ITER H-mode plasmas with various mixes of external heating", R. V. Budny, Nuclear Fus. (2009) <49> 085008 Aug https://iopscience.iop.org/article/10.1088/0029-5515/49/8/085008
  9. ^ "Predictions of H-mode performance in ITER", R. V. Budny, R. Andre, G. Bateman, F. Halpern, C.E. Kessel, A. Kritz and D. McCune Nuclear Fus. (2008) <48> 075005 https://iopscience.iop.org/article/10.1088/0029-5515/48/7/075005
  10. ^ Simulations of deuterium-tritium experiments in TFTR Budny R.V. et al 1992 Nucl. Fusion 32 429 DOI 10.1088/0029-5515/32/3/I07
  11. ^ "Local physics basis of confinement degradation in JET ELMy H mode plasmas and implications for tokamak reactors", R.V. Budny, B. Alper, D.N. Borba, J.G. Cordey, D.R. Ernst, C. Giraud, C.W. Gowers, K. Gunther, T.S. Hahm, G.W. Hammett, Nuclear Fus. (2002) <42> 66 https://iopscience.iop.org/article/10.1088/0029-5515/42/1/310
  12. ^ "A standard DT supershot simulation", R.V. Budny, Nuclear Fusion, Vol 34 (1994) p 1247 https://iopscience.iop.org/article/10.1088/0029-5515/32/3/I07/meta
  13. ^ "Simulations of deuterium-tritium experiments in TFTR" R.V. Budny, M.G. Bell, H. Biglari, M. Bitter, C.E. Bush, C.Z. Cheng, E.D. Fredrickson, B. Grek, K.W. Hill, H. Hsuan, Nuclear Fus. Vol 32 (1992) p 429-447 cphttps://iopscience.iop.org/article/10.1088/0029-5515/32/3/I07/pdf
  14. ^ ``Overview of interpretive modelling of fusion performance in JET DTE2 discharges with TRANSP, Z. Stancar, K.K. Kirov, F. Auriemmansen {\it et al.},` https://doi.org/10.1088/1741-4326/ad0310
  15. ^ 'Improved Confinement with Reversed Magnetic Shear in TFTR' 1995 F. M. Levinton, M. C. Zarnstorff, et al, Phys. Rev. Lett. 75, 4417 DOI: https://doi.org/10.1103/PhysRevLett.75.4417
  16. ^ 'Observation of nonlinear neoclassical pressure-gradient-driven tearing modes in TFTR' 1995 Z. Chang1, J. D. Callen, E. D. Fredrickson, R. V. Budny, et al Phys. Rev. Lett. 74, 4663 DOI: https://doi.org/10.1103/PhysRevLett.74.4663
  17. ^ 'High-temperature plasmas in a tokamak fusion test reactor' 1987 JD Strachan, M Bitter, A T Ramsey, et al, Phys. Rev. Lett. 58, 1004 DOI: https://doi.org/10.1103/PhysRevLett.58.1004
  18. ^ R.V.Budny, et al Predictions of H-mode performance in ITER 2008 Nuclear Fusion 48 075005
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