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Author Contains ("Strain, R. V.")
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Identifier
Title
Creator/Author (s)
Pub Date
909 K
ANL-76-128
Postirradiation examinations of element G-3 from the GCFR F-1 series of mixed-oxide elements after approx. 3 at. % burnup
Strain, R.V.
1980 Sep 01
825 K
ANL/ET/CP--83253; CONF-941207--37
Capabilities for spent fuel characterization at Argonne National Laboratory
Neimark, L.A.
;
Strain, R.V.
1994 Oct 01
872 K
ANL/ET/CP--88825; CONF-9510212--17
Examination of disks from the IPNS depleted uranium target
Strain, R.V.
;
Carpenter, J.M.
1995 Oct 01
130 K
CONF-840701-2
Fission product release and fuel cladding interaction in severe-accident tests of LWR fuel
Strain, R.V.
;
Osborne, M.F.
1983 Nov 01
270 K
ANL/ET/CP-103367
Characteristics of hydride precipitation and reorientation in spent-fuel cladding.
Chung, H. M.
;
Strain, R. V.
;
Billone, M. C.
2000 Nov 14
? K
ANL/ET/CP-107022
Status of LOCA research in high burnup cladding performance program.
Billone, M. C.
;
Strain, R. V.
;
Yan, Y.
2002 Mar 05
405 K
CONF-840701-14
Fission product release from irradiated LWR fuel under accident conditions
Strain, R.V.
;
Sanecki, J.E.
;
Osborne, M.F.
1984 Jan 01
140 K
CONF-881024-3
Fuel relocation mechanism based on microstructures of debris
Strain, R.V.
;
Neimark, L.A.
;
Sanecki, J.E.
1988 May 01
582 K
ANL/ET/CP-94176
Irradiation creep of vanadium-base alloys.
Tsai, H.
;
Matsui, H.
;
Billone, M. C.
; et.al.
1998 May 18
757 K
ANL/ET/CP-94387
Stabilization and disposal of Argonne-West low-level mixed wastes in ceramicrete waste forms.
Barber, D. B.
;
Singh, D.
;
Strain, R. V.
; et.al.
1998 Feb 17
1 Mb
ANL/ET/CP-99539
Stress corrosion cracking behavior of irradiated model austenitic stainless steel alloys.
Chung, H. M.
;
Karlsen, T. M.
;
Ruther, W. E.
; et.al.
1999 Jul 16
241 K
CONF-840914-28
Measurement and characterization of fission products released from LWR fuel
Osborne, M.F.
;
Collins, J.L.
;
Lorenz, R.A.
; et.al.
1984 Jan 01
814 K
CONF-9007149-5
Phase analysis of metallic plutonium-containing fuel alloys using neutron diffraction
Mueller, M.H.
;
Richardson, J.W. Jr.
;
Strain, R.V.
; et.al.
1990 Jan 01
542 K
ANL/ET/CP--92843; CONF-970537--7
Ceramicrete stabilization of low-level mixed wastes - a complete story
Wagh, A.S.
;
Singh, D.
;
Jeong, S.Y.
; et.al.
1997 Mar 01
943 K
ANL/ET/CP-98090
Irradiation-assisted stress corrosion cracking of model austenitic stainless steel.
Chung, H. M.
;
Ruther, W. E.
;
Strain, R. V.
; et.al.
1999 Oct 26
311 K
ANL/CMT/CP-103284
{sup 129}I release fractions in unsaturated tests with fast-flux MOX fuels.
Finn, P. A.
;
Tsai, Y.
;
Goldberg, M. M.
; et.al.
2000 Nov 02
1 Mb
ANL/NT/CP-103306
Metallographic analysis of irradiated RERTR-3 fuel test specimens.
Meyer, M. K.
;
Hofman, G. L.
;
Strain, R. V.
; et.al.
2000 Nov 08
505 K
CONF-860931-14
Results of transient overpower events on breached and unbreached fuel pins
Strain, R.V.
;
Tsai, H.C.
;
Neimark, L.A.
; et.al.
1986 Apr 01
151 K
CONF-881011-40
Fuel-sodium reaction product formation in breached mixed-oxide fuel
Bottcher, J.H.
;
Lambert, J.D.B.
;
Strain, R.V.
; et.al.
1988 Jan 01
? K
ANL/ET/CP-107073
High temperature oxidation of irradiated Limerick BWR cladding.
Yan, Y.
;
Strain, R. V.
;
Bray, T. S.
; et.al.
2002 Mar 13
307 K
CONF-8710111-9
The microstructural and microchemical characterization of samples from the TMI-2 core
Neimark, L.A.
;
Strain, R.V.
;
Sanecki, J.E.
; et.al.
1987 Oct 01
1 Mb
ANL/ET/CP-98708
Stress corrosion cracking of austenitic stainless steel core internal welds.
Chung, H. M.
;
Park, J.-H.
;
Ruther, W. E.
; et.al.
1999 Apr 14
775 K
ANL/TD/CP-98451
Progress in developing very-high-density low-enriched-uranium fuels.
Hayes, S. L.
;
Hofman, G. L.
;
Meyer, M. K
; et.al.
1999 Feb 19
1 Mb
ANL/TD/CP-100148
Initial assessment of radiation behavior of very-high-density low-enriched-uranium fuels.
Hofman, G. L.
;
Meyer, M. L.
;
Snelgrove, J. L.
; et.al.
1999 Oct 01
? K
ANL-01/09
Environmentally assisted cracking in light water reactors : semiannual report, July 2000 - December 2000.
Chopra, O. K.
;
Chung, H. M.
;
Gruber, E. E.
; et.al.
2002 Apr 01
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