THE EFFECTS OF SURFACE CONTAMINATION ON ABSORPTION AND DESORPTION OF DEUTERIUM IN BERYLLIUM AND BERYLLIUM-OXIDE

被引:25
作者
MACAULAYNEWCOMBE, RG
THOMPSON, DA
机构
[1] Department of Engineering Physics, McMaster University, Hamilton
基金
加拿大自然科学与工程研究理事会;
关键词
D O I
10.1016/0022-3115(94)90974-1
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Deuterium thermal absorption and desorption experiments were conducted in high-purity Be, BeO and Be2C samples. Ion-beam analysis was used to measure the surface contamination and near-surface deuterium concentration (up to depths of 500 nm). For bulk BeO the deuterium solubility is small, with S approximate to 10(18) exp(-0.8 eV/kT) at/m(3)(Pa)(1/2) possibly indicative of the formation of hydroxide bonds; the diffusivity is greater than or equal to 7x10(-5) exp(-2.1 eV/kT) m(2)/s. In deliberately corroded Be samples the deuterium surface concentration was about 0.02 at% where there was little or no carbon contamination, and up to 1.6 at% when the carbon and oxygen contents were similar. This implies the presence of large concentrations of trapped deuterium at or near the surface. The approximate solubility of bulk Be2C samples was estimated as 3.4 X 10(27) exp(- 0.58 eV/kT) at/m(3)(Pa)1/2. The solubility for deuterium in bulk Be was found to be 7 x 10(27) exp(-1.0 eV/kT) at/m(3)(Pa)(1/2), and the bulk diffusivity is 8 x 10(-9) exp(- 0.36 eV/kT) m(2)/s.
引用
收藏
页码:942 / 947
页数:6
相关论文
共 30 条
[1]   DEUTERIUM PERMEATION AND DIFFUSION IN HIGH-PURITY BERYLLIUM [J].
ABRAMOV, E ;
RIEHM, MP ;
THOMPSON, DA ;
SMELTZER, WW .
JOURNAL OF NUCLEAR MATERIALS, 1990, 175 (1-2) :90-95
[2]   HYDROGEN TRANSPORT BEHAVIOR OF BERYLLIUM [J].
ANDERL, RA ;
HANKINS, MR ;
LONGHURST, GR ;
PAWELKO, RJ ;
MACAULAYNEWCOMBE, RG .
JOURNAL OF NUCLEAR MATERIALS, 1992, 196 :986-991
[3]   TRITIUM RELEASE FROM IRRADIATED BERYLLIUM AT ELEVATED-TEMPERATURES [J].
BALDWIN, DL ;
SLAGLE, OD ;
GELLES, DS .
JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :329-334
[5]  
BILLONE MC, 1993, 1992 P INT WORKSH CE
[6]   LASER DESORPTION STUDY OF BERYLLIUMS HYDROGEN RECYCLING PROPERTIES AT HIGH-TEMPERATURE [J].
BOIVIN, R ;
TERREAULT, B .
JOURNAL OF NUCLEAR MATERIALS, 1992, 187 (02) :117-121
[7]   TRITIUM RETENTION AND MIGRATION IN BERYLLIUM [J].
CAUSEY, RA ;
HSU, WL ;
MILLS, BE ;
EHRENBERG, J ;
PHILLIPS, V .
JOURNAL OF NUCLEAR MATERIALS, 1990, 176 :654-660
[8]  
CAUSEY RA, 1994, J NUCL MATER, V212
[9]   EFFECTS OF NEUTRON-INDUCED GAS FORMATION ON BERYLLIUM [J].
ELLS, CE ;
PERRYMAN, ECW .
JOURNAL OF NUCLEAR MATERIALS, 1959, 1 (01) :73-84
[10]   T DIFFUSION IN AL2O3 AND BEO/D BEO [J].
FOWLER, JD ;
CHANDRA, D ;
ELLEMAN, TS ;
PAYNE, AW ;
VERGHESE, K .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1977, 60 (3-4) :155-161