Hydrogen release from 800 MeV proton-irradiated tungsten

被引:14
作者
Oliver, BM
Venhaus, TJ
Causey, RA
Garner, FA
Maloy, SA
机构
[1] Pacific NW Natl Lab, Richland, WA 99352 USA
[2] Sandia Natl Labs, Livermore, CA 94550 USA
[3] Los Alamos Natl Lab, Los Alamos, NM 87545 USA
关键词
D O I
10.1016/S0022-3115(02)01293-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Tungsten irradiated in spallation neutron sources, such as those proposed for the accelerator production of tritium (APT) project, will contain large quantities of generated helium and hydrogen gas. Tungsten used in proposed fusion reactors will also be exposed to neutrons, and the generated protium will be accompanied by deuterium and tritium diffusing in from the, plasma-facing surface. The release kinetics of these gases during various off-normal scenarios, involving loss of coolant and after heat-induced rises in temperature are of particular interest for both applications I. To determine the release kinetics of hydrogen from tungsten, tungsten rods irradiated with 800 MeV protons in the Los Alamos Neutron Science Center (LANSCE) to high exposures as part of the APT project have been. examined. Hydrogen evolution from the tungsten has been measured using a dedicated mass-spectrometer system by subjecting the specimens to an essentially linear temperature ramp from similar to300 to similar to1500 K. Release profiles are compared with predictions obtained using the Tritium Migration Analysis Program (TMAP4). The measurements show that for high proton doses, the majority of the hydrogen is released gradually, starting at about 900 K and reaching a maximum at about 1400 K, where it drops fairly rapidly. Comparisons with TMAP show quite reasonable agreement using a trap energy of 1.4 eV and a trap density of similar to7%. There is a small additional release fraction occurring at similar to550 K, which is believed to be associated with low-energy trapping at or near the surface, and, therefore, was not included in the bulk TMAP model. Published by Elsevier Science B.V.
引用
收藏
页码:1418 / 1423
页数:6
相关论文
共 12 条
[1]   DEUTERIUM TRANSPORT AND TRAPPING IN POLYCRYSTALLINE TUNGSTEN [J].
ANDERL, RA ;
HOLLAND, DF ;
LONGHURST, GR ;
PAWELKO, RJ ;
TRYBUS, CL ;
SELLERS, CH .
FUSION TECHNOLOGY, 1992, 21 (02) :745-752
[2]   The use of tungsten in fusion reactors: A review of the hydrogen retention and migration properties [J].
Causey, RA ;
Venhaus, TJ .
PHYSICA SCRIPTA, 2001, T94 :9-15
[3]  
ELEVELD H, 1992, J NUCL MATER, V191, P433
[4]   VOID GROWTH AND THERMAL-DESORPTION OF DEUTERIUM FROM VOIDS IN TUNGSTEN [J].
ELEVELD, H ;
VANVEEN, A .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :1421-1425
[5]   SOLUTION AND DIFFUSION OF HYDROGEN IN TUNGSTEN [J].
FRAUENFELDER, R .
JOURNAL OF VACUUM SCIENCE & TECHNOLOGY, 1969, 6 (03) :388-+
[6]   Determination of helium and hydrogen yield from measurements on pure metals and alloys irradiated by mixed high energy proton and spallation neutron spectra in LANSCE [J].
Garner, FA ;
Oliver, BM ;
Greenwood, LR ;
James, MR ;
Ferguson, PD ;
Maloy, SA ;
Sommer, WF .
JOURNAL OF NUCLEAR MATERIALS, 2001, 296 :66-82
[7]  
*LOS AL NAT LAB, 1994, LACP9427 LOS AL NAT
[8]  
MALOY SA, 1997, P TOP M NUCL APPL AC, P58
[9]  
MERRILL BJ, EGGFSP10315 INEL EG
[10]   Hydrogen release from 800-MeV proton-irradiated tungsten rods [J].
Oliver, BM ;
Garner, FA ;
Hamilton, ML ;
Venhaus, TJ ;
Causey, RA ;
Maloy, SA .
PHYSICA SCRIPTA, 2001, T94 :137-140