Post-irradiation studies of beryllium reflector of fission reactor - Examination of gas release, swelling and structure of beryllium under annealing

被引：20

作者：

Andreev, DV ^{[1
]}

Bespalov, VN ^{[1
]}

Birjukov, AJ ^{[1
]}

Gurovich, BA ^{[1
]}

Platonov, PA ^{[1
]}

机构：

[1] RUSSIAN RES CTR, KURCHATOV INST, MOSCOW 123182, RUSSIA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1996年 / 233卷

关键词：

D O I：

10.1016/S0022-3115(96)00289-9

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Hot-pressed high-density (TShG-type) beryllium was irradiated at 100 degrees C up to the fast neutron fluence of 1 x 10(26) n/m(2). Transmutation tritium and helium contents were 652 and 4400 appm, respectively. Post-irradiation studies of beryllium consist of optical and electron microscopy, density measurements before and after isochronal annealing at the temperature range of 300-1100 degrees C and thermodesorption gas spectrometry. Investigation shows the following: (1) Slight swelling of beryllium after neutron irradiation. (2) Spatial non-uniformity in the distribution of the pores. (3) Complicated dependence of swelling on annealing temperature caused by formation of gas porosity. In the temperature range from 500 to 800 degrees C, swelling of beryllium was probably caused by growth of bubbles because of tritium mobility. At the temperature above 900 degrees C swelling of beryllium was probably caused by growth of bubbles because of helium mobility. (4) Full degassing of the irradiated beryllium took place below its melting temperature.

引用

页码：880 / 885

页数：6

共 6 条

[1]

ARKHANGELSKII NV, 1983, IAE38615 PREPRINT

[2] TRITIUM RELEASE FROM IRRADIATED BERYLLIUM AT ELEVATED-TEMPERATURES [J].

BALDWIN, DL ;

SLAGLE, OD ;

GELLES, DS .

JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :329-334

[3]

Billone M.C., 1991, Fusion Technol, V19, P1707

[4]

BILLONE MC, 1993, P INT WORKSHOP C JAN

[5]

*ITER CONC DES, 1990, 7 IAEA ITER DS INT R

[6]

NARDI C, STATUS KNOWLEDGE BER

← 1 →