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SOME ASPECTS OF EFFECTS OF FISSION FRAGMENT IRRADIATION UPON OXIDATION OF AUSTENITIC STAINLESS STEELS BY OXYGEN AT 650 DEGREES AND 800 DEGREES C
被引:9
作者
:
BENNETT, MJ
论文数:
0
引用数:
0
h-index:
0
机构:
Solid State Division, UKAEA Research Group, Atomic Energy Research Establishment, Harwell, Didcot, Berks.
BENNETT, MJ
CHAFFEY, GH
论文数:
0
引用数:
0
h-index:
0
机构:
Solid State Division, UKAEA Research Group, Atomic Energy Research Establishment, Harwell, Didcot, Berks.
CHAFFEY, GH
ANTILL, JE
论文数:
0
引用数:
0
h-index:
0
机构:
Solid State Division, UKAEA Research Group, Atomic Energy Research Establishment, Harwell, Didcot, Berks.
ANTILL, JE
机构
:
[1]
Solid State Division, UKAEA Research Group, Atomic Energy Research Establishment, Harwell, Didcot, Berks.
来源
:
JOURNAL OF NUCLEAR MATERIALS
|
1969年
/ 32卷
/ 02期
关键词
:
D O I
:
10.1016/0022-3115(69)90079-8
中图分类号
:
T [工业技术];
学科分类号
:
08 ;
摘要
:
The oxidation of an 18/8/Ti stainless steel by oxygen at 650 °C for varying periods up to 3760 h was enhanced by a fission fragment flux between 6.2 × 108 and 1.7 × 109 ff/cm2.sec but was not influenced by the associated incident reactor radiation. The enhancement increased with exposure, such that the magnitude of oxidation on the specimens irradiated with fission fragments was greater than on the controls by a factor of between 1.3-3.5 and 1.7-4.6 after 1000 and 3700 h respectively. There was no systematic correlation between the extent of the increased attack and the magnitude of the fission-fragment flux. The radiation-induced attack would appear to be primarily localised as mounds and is believed to be caused by displacement damage in the protective oxide film as a direct result of fission recoil bombardment. Fission-fragment irradiation did not influence significantly, however, either the magnitude of oxidation or the percentage of non-adherent oxide formed during the oxidation of a 20/25/Nb stainless steel at 800 °C. The exposure period varied up to 4252 h and the fission fragment flux was between 1.13 and 1.53 × 109 ff/cm2-sec. The absence of any irradiation effect at this temperature contrasts with the radiation-enhanced oxidation of this steel observed previously at 650 °C. © 1969.
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页码:299 / &
相关论文
共 6 条
[1]
ANTILL JE, 1964, 3 P GEN C PEAC US AT, V9, P523
[2]
Bennett M. J., 1968, Laboratory Practice, V17, P1230
[3]
EFFECT OF FISSION FRAGMENT IRRADIATION UPON OXIDATION OF A 20 WT PERCENT CR 25 WT PERCENT NI NB STABILISED STAINLESS STEEL BY OXYGEN AT 650 DEGREES C
BENNETT, MJ
论文数:
0
引用数:
0
h-index:
0
BENNETT, MJ
CHAFFEY, GH
论文数:
0
引用数:
0
h-index:
0
CHAFFEY, GH
BLYTHE, PC
论文数:
0
引用数:
0
h-index:
0
BLYTHE, PC
ANTILL, JE
论文数:
0
引用数:
0
h-index:
0
ANTILL, JE
[J].
JOURNAL OF NUCLEAR MATERIALS,
1967,
21
(01)
: 1
-
&
[4]
BENNETT MJ, 1967, NUCL ENG, V12, P758
[5]
BILLINGTON SR, 1960, TID7597 USAEC REP, P733
[6]
BOARD J, 1967, TRGR1507 UKAEA REP
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1
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共 6 条
[1]
ANTILL JE, 1964, 3 P GEN C PEAC US AT, V9, P523
[2]
Bennett M. J., 1968, Laboratory Practice, V17, P1230
[3]
EFFECT OF FISSION FRAGMENT IRRADIATION UPON OXIDATION OF A 20 WT PERCENT CR 25 WT PERCENT NI NB STABILISED STAINLESS STEEL BY OXYGEN AT 650 DEGREES C
BENNETT, MJ
论文数:
0
引用数:
0
h-index:
0
BENNETT, MJ
CHAFFEY, GH
论文数:
0
引用数:
0
h-index:
0
CHAFFEY, GH
BLYTHE, PC
论文数:
0
引用数:
0
h-index:
0
BLYTHE, PC
ANTILL, JE
论文数:
0
引用数:
0
h-index:
0
ANTILL, JE
[J].
JOURNAL OF NUCLEAR MATERIALS,
1967,
21
(01)
: 1
-
&
[4]
BENNETT MJ, 1967, NUCL ENG, V12, P758
[5]
BILLINGTON SR, 1960, TID7597 USAEC REP, P733
[6]
BOARD J, 1967, TRGR1507 UKAEA REP
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1
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