50 Matching Results

Search Results

Results: 1 - 24 next
Primary view of Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures
White, L.S. & Busby, C.C.
March 1978
Primary view of The in-Pile Thermal Conductivity of Selected ThO$Sub 2$--UO$Sub 2$ Fuels at Low Depletions
Jacobs, D. C.
May 1969
Primary view of Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking
Polan, N. W. & Tucker, R. P.
December 1977
Primary view of Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods
Clayton, J. C.
August 1985
Primary view of Determination of statistically based design limits associated with engineering models.
Ginsburg, H.
February 1, 1980
Primary view of Thoria powder process development
Hutchison, C.R. & Lloyd, R.
October 1, 1979
Primary view of Fuel rod-grid interaction wear: in-reactor tests
Stackhouse, R. M.
November 1, 1979
Primary view of Model for incorporating fuel swelling and clad shrinkage effects in diffusion theory calculations
Schick, W.C. Jr.; Milani, S. & Duncombe, E.
March 1, 1980
Primary view of Effect of fuel chips on cladding stress in zircaloy clad oxide fuel rods
Yerman, J. F.
November 1978
Primary view of Nondestructive assay of UO/sub 2/--ThO/sub 2/ fuel pellets using the delayed neutron pellet assay gage
Emert, C.J.; Milani, S. & Beggs, W.J.
June 1, 1979
Primary view of Design features of the Light Water Breeder Reactor (LWBR) which improve fuel utilization in light water reactors
Hecker, H. C. & Freeman, L .B.
August 1981
Primary view of Corrosion of Zircaloy-4 tubing in 68OF water
Marino, G. P. & Fischer, R. L.
December 1, 1978
Primary view of ASBLT: a system of DATATRAN MODULES which process core fuel loading for use in as-built calculations
Beaudoin, B.R.; Beggs, W.J.; Case, C.R. & Wilczynski, R.
February 1, 1979
Primary view of AIRWAY: a fortran computer program to estimate radiation dose commitments to man from the atmospheric release of radionuclides
Rider, J. L.
June 1979
Primary view of Out-of-pile hydriding and thermal relaxation of reactor fasteners using Zircaloy components: the REM-120 test.
Duenkel, D.A.
January 1, 1980
Primary view of Results of initial nuclear tests on LWBR
Sarber, W. K.
June 1, 1979
Primary view of Effect of simulated thermal shield motion on nuclear instrument response: measurements and calculations
Schick, W. C., Jr.; Emert, C. J.; Shure, K. & Natelson, M.
August 1, 1979
Primary view of Shippingport operations with the Light Water Breeder Reactor core.
Budd, W. A.
March 1, 1986
Primary view of FLASH6 simulation of semiscale blowdown data, NRC Standard Problems 2 and 3
Harris, B.D.; Prelewicz, D.A. & Beus, S.G.
September 1, 1979
Primary view of Iodine and cesium in oxide fuel pellets and zircaloy-4 cladding of irradiated fuel rods
Ivak, D. M. & Waldman, L. A.
March 1, 1979
Primary view of Internal hydriding in irradiated defected Zircaloy fuel rods: A review
Clayton, J C
October 1, 1987
Primary view of Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station
Massimino, R.J. & Williams, D.A.
May 1, 1983
Primary view of End-of-life destructive examination of light water breeder reactor fuel rods
Richardson, K.D.
October 1, 1987
Primary view of PDQ-8 reference manual
Pfiefer, C J & Spitz, C J
May 1, 1978
Back to Top of Screen