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Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning: Applied to hydrogen uptake and release from tungsten

Journal Article · · Journal of Nuclear Materials
 [1];  [1];  [2];  [1];  [1];  [3]
  1. Univ. of California, San Diego, CA (United States). Center for Energy Research
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Univ. of California, San Diego, CA (United States). Center for Energy Research; Univ. of California, San Diego, CA (United States). Dept. of Mechanical and Aerospace Engineering (MAE)
Simulating the implantation and thermal desorption evolution in a reaction-diffusion model requires solving a set of coupled differential equations that describe the trapping and release of atomic species in Plasma Facing Materials (PFMs). These fundamental equations are well outlined by the Tritium Migration Analysis Program (TMAP) which can model systems with no more than three active traps per atomic species. To overcome this limitation, we have developed a Pseudo Trap and Temperature Partition (PTTP) scheme allowing us to lump multiple inactive traps into one pseudo trap, simplifying the system of equations to be solved. For all temperatures, we show the trapping of atoms from solute is exactly accounted for when using a pseudo trap. However, a single effective pseudo trap energy can not well replicate the release from multiple traps, each with its own detrapping energy. However, atoms held in a high energy trap will remain trapped at relatively low temperatures, and thus there is a temperature range in which release from high energy traps is effectively inactive. By partitioning the temperature range into segments, a pseudo trap can be defined for each segment to account for multiple high energy traps that are actively trapping but are effectively not releasing atoms. With increasing temperature, as in controlled thermal desorption, the lowest energy trap is nearly emptied and can be removed from the set of coupled equations, while the next higher energy trap becomes an actively releasing trap. Each segment is thus calculated sequentially, with the last time step of a given segment solution being used as an initial input for the next segment as only the pseudo and actively releasing traps are modeled. This PTTP scheme is then applied to experimental thermal desorption data for tungsten (W) samples damaged with heavy ions, which display six distinct release peaks during thermal desorption. Without modifying the TMAP7 source code the PTTP scheme is shown to successfully model the D retention in all six traps. In conclusion, we demonstrate the full reconstruction from the plasma implantation phase through the controlled thermal desorption phase with detrapping energies near 0.9, 1.1, 1.4, 1.7, 1.9 and 2.1 eV for a W sample damaged at room temperature.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-06NA25396; FG02-07ER54912; SC0001999
OSTI ID:
1441352
Alternate ID(s):
OSTI ID: 1548125
OSTI ID: 22752139
Report Number(s):
LA-UR--18-21486
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 508; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (10)

Deuterium retention in tungsten in dependence of the surface conditions journal March 2003
The effect of inert gas pre-irradiation on the retention of deuterium in tungsten: A TMAP investigation combined with first-principles method journal October 2017
Modelling deuterium release during thermal desorption of D+-irradiated tungsten journal March 2008
Tungsten as material for plasma-facing components in fusion devices journal August 2011
Reduced deuterium retention in simultaneously damaged and annealed tungsten journal October 2017
Surface modifications and deuterium retention in polycrystalline and single crystal tungsten as a function of particle flux and temperature journal November 2017
Deuterium atom loading of self-damaged tungsten at different sample temperatures journal December 2017
On the use of SRIM for computing radiation damage exposure journal September 2013
Ion-driven deuterium retention in tungsten journal February 2008
Hydrogen isotope transport across tungsten surfaces exposed to a fusion relevant He ion fluence journal May 2017

Cited By (2)

Time-resolved laser-induced desorption spectroscopy (LIDS) for quantified in-situ hydrogen isotope retention measurement and removal from plasma facing materials journal July 2019
Plasma-Material-Interaction Research Using PISCES Linear Plasma Devices journal October 2019

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