Environmental Engineering Reference
In-Depth Information
2.
C.O. Smith ,
Nuclear Reactor Materials
, Addison-Wesley, Reading, MA , USA ,
1967 .
3.
J.T.A.
Roberts ,
Structural Materials in Nuclear Power Systems
,
Plenum
Publishing , New York, NY, USA , 1981 .
4.
H.G. Rickover ,
History of Development of Zirconium Alloys for Use in Nuclear
Power Reactors
, US ERDA, NR&D,Washington, DC, USA, 1975; see also
R. Krishnan and M.K. Asundi, 'Zirconium alloys in nuclear technology', in
Ally Design
, S. Ranganathan, V.S. Arunachalam and R.W. Cahn (eds), Indian
Academy of Sciences, Bangalore, India (1981) 139-154.
5 .
G . S . W a s ,
Fundamentals of Radiation Materials Science
, Springer , New York,
NY, USA , 2007 .
6.
G.R. Odette and G.E. Lucas , ' Recent progress to understanding reactor pressure
vessel embrittlement',
Radiation Effects Defects Solids
,
144
( 1998 ) 189 -231.
7.
R.G. Carter , N. Soneda , K. Dohi , J.M. Hyde , C.A. English and W.L. Server ,
'Microstructural characterization of irradiation-induced Cu-enriched clusters
in reactor pressure vessel steels',
J. Nucl. Mater
.,
298
( 2001 ) 211 -224.
8.
M. Meyers and K. Chawla ,
Mechanical Behavior of Materials
, Cambridge
University Press , New York , 2009 .
9.
G.E. Dieter ,
Mechanical Metallurgy
, McGraw-Hill , New York , 1988 .
10.
J. Roester , H. Harders and M. Baeker ,
Mechanical Behaviour of Engineering
Materials
, Springer , New York , 2006 .
11.
D.M.R. Taplin and A.L. Collins , Fracture at high temperatures under cyclic
loading ',
Ann. Rev. Mater. Sci
.,
8
( 1978 ) 235 .
12.
L.F. Coffi n, 'A note on low cycle fatigue laws',
J. Mater
.,
6
( 1971 ) 388 -402.
13.
S.S. Manson , 'Challenge to unify treatment of high temperature fatigue - par-
tisan proposal based on strain-range partitioning', in
Symposium on 'Fatigue
at Elevated Temperatures
', ASTM STP 520 Storrs, CT, American Society for
Testing and Materials (1972) 744-782.
14.
S. Majumdar and P.S. Maiya , 'A unifi ed and mechanistic approach to
creep-fatigue damage', in
Proceedings of the International Conference on
Mechanical Behavior of Materials
, ICM-II, American Society for Metals, Metals
Park , Ohio ( 1976 ) 924-928.
15.
K.L. Murty and J.R. Holland , ' Low-cycle fatigue characteristics of irradiated
304SS ',
Nucl. Technol
.,
58
( 1982 ) 530 -537.
16.
L.K. Mansur , ' Theory and experimental background on dimensional changes in
irradiated alloy',
J. Nucl. Mater
.,
216
( 1994 ) 97 -123.
17.
M. Kiritani , ' Microstructure evolution during irradiation ',
J. Nucl. Mater
.,
216
( 1994 ) 220 -264.
18.
D.R. Olander , 'Fundamentals aspects of nuclear reactor fuel elements', National
Technical Information Service, U.S. Department of Commerce, Springfi eld, VA,
1976 .
19.
M.J. Makin and F.J. Minter , ' Irradiation hardening in copper and nickel ',
Acta
Metall
.,
8
( 1960 ) 691 -699.
20.
K.L. Murty , ' Role and signifi cance of source hardening in radiation embrittle-
ment of iron and ferritic steels',
J. Nucl. Mater
.,
270
( 1999 ) 115 -128.
21.
T.S. Byun and K. Farrell , ' Plastic instability in polycrystalline metals after low
temperature irradiation',
Acta Mater
.,
52
( 2004 ) 1597 -1608.
Search WWH ::
Custom Search