Modeling of fuel retention in the pre-damaged tungsten with MeV W ions after exposure to D plasma. (December 2017)
- Record Type:
- Journal Article
- Title:
- Modeling of fuel retention in the pre-damaged tungsten with MeV W ions after exposure to D plasma. (December 2017)
- Main Title:
- Modeling of fuel retention in the pre-damaged tungsten with MeV W ions after exposure to D plasma
- Authors:
- Wang, Zhenhou
Sang, Chaofeng
Liu, Shengguang
Chang, Mingyu
Sun, Jizhong
Wang, Dezhen - Abstract:
- Highlights: The code was validated against the experimental data to study the fuel retention inside the pre-damaged W material. The modeling results confirm the conclusions of previous works that the irradiation-induced traps play a dominated role on the fuel retention in the surface of the material (∼ micrometer). Abstract: Modeling of high-Z ion irradiated-induced damages on fuel retention inside tungsten (W) material has been performed in this work. The upgraded Hydrogen Isotope Inventory Processes Code (HIIPC) is applied to model the deuterium (D) retention inside pre-damaged W during exposed to low-energy D flux, and the W is pre-irradiated by 20 MeV W-ion before exposed to D flux. Three types of trap, i.e. mono-vacancies, dislocations and grain boundary vacancies, are considered in the present model. The mono-vacancy defects induced by energetic W ions are calculated by SRIM code. First, the model is validated against the available experimental data under the same D flux exposure conditions, showing the reasonable agreement. Then, the effect of radiation-induced defects produced by pre-exposed energetic W-ion with different energy and fluence on the fuel retention are studied, confirming that the irradiation-induced traps play a dominated role on the fuel retention in the surface of the material (∼ micrometer). Finally, the effects of different type of defect, D fluence, and wall temperature on the fuel retention are discussed systemically, and these modeling resultsHighlights: The code was validated against the experimental data to study the fuel retention inside the pre-damaged W material. The modeling results confirm the conclusions of previous works that the irradiation-induced traps play a dominated role on the fuel retention in the surface of the material (∼ micrometer). Abstract: Modeling of high-Z ion irradiated-induced damages on fuel retention inside tungsten (W) material has been performed in this work. The upgraded Hydrogen Isotope Inventory Processes Code (HIIPC) is applied to model the deuterium (D) retention inside pre-damaged W during exposed to low-energy D flux, and the W is pre-irradiated by 20 MeV W-ion before exposed to D flux. Three types of trap, i.e. mono-vacancies, dislocations and grain boundary vacancies, are considered in the present model. The mono-vacancy defects induced by energetic W ions are calculated by SRIM code. First, the model is validated against the available experimental data under the same D flux exposure conditions, showing the reasonable agreement. Then, the effect of radiation-induced defects produced by pre-exposed energetic W-ion with different energy and fluence on the fuel retention are studied, confirming that the irradiation-induced traps play a dominated role on the fuel retention in the surface of the material (∼ micrometer). Finally, the effects of different type of defect, D fluence, and wall temperature on the fuel retention are discussed systemically, and these modeling results are in well agreement with the previous studies. … (more)
- Is Part Of:
- Nuclear materials and energy. Volume 13(2017)
- Journal:
- Nuclear materials and energy
- Issue:
- Volume 13(2017)
- Issue Display:
- Volume 13, Issue 2017 (2017)
- Year:
- 2017
- Volume:
- 13
- Issue:
- 2017
- Issue Sort Value:
- 2017-0013-2017-0000
- Page Start:
- 1
- Page End:
- 7
- Publication Date:
- 2017-12
- Subjects:
- Fuel retention -- Tungsten -- Irradiated-induced damage
Nuclear energy -- Periodicals
Nuclear fuels -- Periodicals
Nuclear reactors -- Materials -- Periodicals
Radioactive substances -- Periodicals
621.4833 - Journal URLs:
- http://www.sciencedirect.com/science/journal/23521791 ↗
http://www.sciencedirect.com/ ↗ - DOI:
- 10.1016/j.nme.2017.08.004 ↗
- Languages:
- English
- ISSNs:
- 2352-1791
- 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 HMNTS - ELD Digital store - Ingest File:
- 5510.xml