Skip to Main Content
Skip Nav Destination
ASTM Selected Technical Papers
Effects of Radiation on Materials: 22nd Symposium
By
TR Allen
TR Allen
1
Symposium Chair and Editor
?
University of Wisconsin
?
Madison, Wisconsin
Search for other works by this author on:
RG Lott
RG Lott
2
Symposium Co-Chair and Editor
?
Westinghouse Electric Company
?
Pittsburgh, Pennsylvania
Search for other works by this author on:
JT Busby
JT Busby
3
Symposium Co-Chair and Editor
?
Oak Ridge National Laboratory
Search for other works by this author on:
AS Kumar
AS Kumar
4
Symposium Co-Chair and Editor
?
University of Missouri-Rolla
?
Rolla, Missouri
Search for other works by this author on:
ISBN-10:
0-8031-3401-0
ISBN:
978-0-8031-3401-0
No. of Pages:
406
Publisher:
ASTM International
Publication date:
2006

In order to investigate the neutron flux effect on the irradiation hardening of type 304 stainless steel, microstructure observation, tensile test, and micro Vickers hardness test were performed on the type 304 stainless steel irradiated to 1.6 × 1024-1.4 × 1026 n/m2 in LWRs, (flux 3.4 × 1015-5.6 × 1017 n/m2/s). The tensile test was carried out in air at 288°C, and the hardness test was also carried out in air, but at room temperature. The amount of irradiation hardening increased with increasing neutron flux. The amount of irradiation hardening was proportional to the 0.25th power of neutron flux. Dislocation loop density increased with increasing neutron flux, and mean diameter had hardly any dependence on neutron flux. From the above, the neutron flux dependence of dislocation loop density could be said to be the main factor controlling irradiation hardening under LWR irradiation conditions. The amount of irradiation hardening of type 304 stainless steel used in LWR is expected to be lower than the predicted amount from higher flux irradiated materials.

1.
Yanagita
,
S.
,
Yoshiie
,
T.
, and
Ino
,
H.
, “
Model Calculation for Irradiation Rate Dependence of Defect Structure in Fe-Cu ally
,”
J. Japan Inst. Metals
 0021-4876, Vol.
64
, No.
2
,
2000
, pp. 115–124.
2.
Stoller
,
R. E.
, “
Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering
,”
Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270
,
Gelles
D. S.
,
Nanstad
R. K.
,
Kumar
A. S.
, and
Little
E. A.
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
.
3.
Stoller
,
R. E.
, “
Modeling the Influence of Irradiation Temperature and Displacement Rate on Radiation-Induced Hardening in Ferritic Steels
,”
Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175
,
Kumar
A. S.
,
Gelles
D. S.
,
Nanstad
R. K.
, and
Little
Edward A.
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1993
.
4.
Yoshitake
,
T.
,
Donomae
,
T.
,
Mizuta
,
S.
,
Tsai
,
H.
,
Strain
,
R. V.
,
Allen
,
T.
, et al
, “
Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II under Lower-Dose-Rate Conditions to High Fluence
,”
ASTM STP 1405
,
ASTM International
,
West Conshohocken, PA
,
2001
, pp. 469–486.
5.
Muroga
,
T.
,
Watanabe
,
H.
, and
Yoshida
,
N.
, “
Correlation of Fast Neutron. Fusion Neutron and Electron Irradiations Based on the Dislocation Loop Density
,”
J. Nucl. Mater.
 0022-3115,
174
,
1990
, pp. 282–288.
6.
Fleischer
,
R. L.
, “
Solution Hardening by Tetragonal Distortions: Application to Irradiation Hardening in f.c.c. Crystal
,”
Acta Met.
 0001-6160,
10
,
1962
, pp. 834–842.
This content is only available via PDF.
You do not currently have access to this chapter.
Close Modal

or Create an Account

Close Modal
Close Modal