Predictive modeling for performance assessment of ITER-like divertor in China Fusion Engineering Testing Reactor
- 1. Department of Applied Physics, Donghua University, Shanghai (China)
- 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China)
- 3. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei (China)
Description
To facilitate the design of the China Fusion Engineering Testing Reactor (CFETR), predictive modeling for the assessment and optimization of the divertor performances is an indispensable approach. This paper presents the modeling of the edge plasma behaviors as well as the W erosion and transport properties in CFETR with ITER-like divertor by using the B2-Eirene/SOLPS 5.0 code package together with the Monte Carlo impurity transport code DIVIMP. As expected, SOLPS modeling of divertor-SOL plasmas finds that the peak heat flux onto the divertor targets greatly exceeds 10 MW/m2, an engineering limit posed to the steady-state and/or long-pulse operation of the next-step fusion devices, for a wide range of plasma conditions, and thus modeling of Ar puffing by scanning the puffing rate for radiative divertor is performed. As the increase of the Ar puffing rate, the peak target heat fluxes and plasma temperature decreases exponentially, reflecting that Ar puffing is highly effective at power exhausting. Based on the ion fluxes from from SOLPS, the W erosion is calculated by taking into consideration the bombardment of both D and Ar ions, and then the W plasma concentrations are calculated based on the W erosion fluxes using DIVIMP. The calculations show that if the Ar puffing only being used to reduce the divertor heat load, the W plasma contamination in the core plasma is a little bit high, which demonstrates that some further upgrading of the divertor geometry is still needed. (author)
Files
50040048.pdf
Files
(2.2 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:704a18244510c4dba774ef7f79c76730
|
2.2 MB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Proceeding of A3 foresight program seminar on critical physics issues specific to steady state sustainment of high-performance plasmas 2016
- Imprint Pagination
- [200 p.]
- Journal Page Range
- p. 69-83
- Report number
- NIFS-PROC--108
Conference
- Title
- A3 foresight program seminar on critical physics issues specific to steady state sustainment of high-performance plasmas 2016
- Dates
- 22-25 Nov 2016
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50040048
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING RATIO; CYCLOTRON RADIATION; DIVERTORS; ELECTRIC CURRENTS; EROSION; HEAT FLUX; ITER TOKAMAK; MONTE CARLO METHOD; PLASMA IMPURITIES; PLASMA SIMULATION; THERMONUCLEAR REACTOR MATERIALS; TRITIUM; TUNGSTEN
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BREMSSTRAHLUNG; CALCULATION METHODS; CLOSED PLASMA DEVICES; CONVERSION RATIO; CURRENTS; DIMENSIONLESS NUMBERS; ELECTROMAGNETIC RADIATION; ELEMENTS; HYDROGEN ISOTOPES; IMPURITIES; ISOTOPES; LIGHT NUCLEI; MATERIALS; METALS; NUCLEI; ODD-EVEN NUCLEI; RADIATIONS; RADIOISOTOPES; REFRACTORY METALS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 34 refs., 11 figs., 2 tabs.