Environmental Engineering Reference
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69.
D.R. Olander , 'Light water fuel designs and performances,' in Concise
Encyclopedia of Materials for Energy Systems ', J.W. Martin (ed.), Elsevier
( 2000 ), 31.
70.
P.L. Anderson , 'Irradiation assisted stress corrosion cracking,' in Material
Performance and Evaluation , R.H. Jones (ed.), ASM International , Materials
Park, OH ( 1998 ) 181.
71.
D.G. Franklin and R.B. Adamson , ' Implications of Zircaloy creep and growth
to light water reactor performance', J. Nucl. Mater ., 159 ( 1988 ) 12 -21.
72.
K. Edsinger , ' Review of fuel degradation in BWRs ', in Proceedings of
International Topical Meeting on LWR Fuel Performance ', ANS ( 2000 ) 523 .
73.
K. Sakamoto and M. Nakatsuka , ' Stress reorientation of hydrides ', J. Nucl. Sci.
Tech ., 43 ( 2006 ) 1136 -1141.
74.
A.M. Garde , 'Effects of irradiation and hydriding on the mechanical proper-
ties of Zircaloy-4 at high fl uence', in Zirconium in the Nuclear Industry, 8th
International Symposium , ASTM STP 1023, L.P. Van Swam and C.M. Eucken
(eds), American Society for Testing and Materials, Philadelphia, PA (1989)
548-569.
75.
K. Edsinger , J.H. Davies and R.B. Adamson , 'Degraded fuel cladding fractog-
raphy and fracture behavior', in 12th International Symposium on 'Zirconium
in the Nuclear Industry , ASTM STP 1354, G.P. Sabol and G.D. Moan (eds),
American Society for Testing and Materials, Philadelphia, PA (1999) 316-339.
76.
J.A. Kuszyk et al ., Interim Report, Zion Unit 1 Cycle 6, Fuel Performance, EPRI
Project RP611-1, WCAP-10280.
77.
T.C. Rowland and S. Gehl , BWR Fuel Rod Performance Evaluation Program,
EPRI Report NP-4602 (1986).
78.
'Review of fuel failures in water cooled reactors', IAEA Nuclear Energy Series
No. NF-T-2.1, International Atomic Energy Agency, Vienna (2010).
79.
G. Srikant , B. Marple , I. Charit and K.L. Murty , ' Characterization of stress rup-
ture behavior of cp-Ti via burst testing', Mat Sci Eng ., A463 ( 2007 ) 203 -207.
80.
Y. Zhou , B. Devarajan and K.L. Murty , ' Short-term rupture studies of Zircaloy-4
and Nb-modifi ed Zircaloy-4 tubing using closed-end internal pressurization',
Nucl. Eng. Design , 228 ( 2004 ) 3 -13.
81.
C.S. Seok , B. Marple , Y.J. Song , S. Gollapudi , I. Charit and K.L. Murty , ' High
temperature deformation characteristics of Zirlo™ tubing via ring-creep and
burst tests', Nucl. Eng. Design , 241 ( 2011 ) 599 -602.
￿ ￿ ￿ ￿ ￿ ￿
82.
K.L. Murty , 'Applications of crystallographic textures of zirconium alloys in
nuclear industry', in Zirconium in the Nuclear Industry: Eighth Symposium ,
ASTM STP 1023, Swam and C.M. Eucken (eds), American Society for Testing
and Materials , Philadelphia, PA ( 1989 ) 570-595.
83.
K.L. Murty , ' Creep studies for life-prediction in water reactors ', J. Metals , Oct.
( 1999 ) 32 -39.
84.
R. Kishore , S. Banerjee and P. Rama Rao , ' First report on observation of
abnormal creep in Zr-2.5%wt%Nb alloy at low stress', J. Mater. Sci ., 44 ( 2009 )
2247 -2256.
85.
K.L. Murty , ' Deformation mechanisms and transients in creep of zircaloys:
applications to nuclear technology', Trans. IIM , 53 ( 2000 ) 107 -120.
86.
S. Gollapudi , I. Charit and K.L. Murty , ' Creep mechanisms in Ti-3Al-2.5V
alloy tubing deformed under closed-end internal gas pressurization', Acta Mat .,
56 ( 2008 ) 2406 -2419.
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