Nodalization study of the Westinghouse Model E steam generator secondary side /

Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS.
Published: (1982)

Loss of thermal sleeves in reactor coolant system piping at certain Westinghouse Pwr power plants.
Published: (1982)

Modified heat transfer coefficient in the presence of noncondensible gas for RELAP5/MOD2 computer code /
by: Grant, Sharon Elizabeth, 1965-
Published: (1990)

Dynamics of fluid-structure systems in the energy industry : presented at the third National Congress on Pressure Vessel and Piping, San Francisco, California, June 25-29, 1979 /
Published: (1979)

Project of a 420 MW atomic electric station.
Published: (1957)

Thermal instability of a volumetrically heated pool with phase change and a free upper surface /
by: Yao, L. S.
Published: (1978)

Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports".
Published: (1980)

Analysis with TRACE code of Rosa test 1.2 : small LOCA in the hot-leg with HPI and accumulator actuation /
by: Muñoz-Cobo, J. L.
Published: (2013)

Development of horizontal off-take model for application to reactor headers of CANDU type reactors /
Published: (2010)

Validation of systems transients analysis codes : presented at the 1995 ASME/JSME Fluids Engineering and Laser Anemometry Conference and Exhibition, August 13-18, 1995, Hilton Head, South Carolina /
Published: (1995)

Effect of radiation on hydraulic snubber fluid.
Published: (1980)

Assessment of PWR steam generator modelling in RELAP5/MOD2 /
by: Putney, J. M., et al.
Published: (1993)

Development of a high speed fluorescent particle image velocimetry technique to study steam bubble collapse /
by: Philip, Olivier G., 1968
Published: (1993)

CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident /
by: Boyd, Christopher Fred, et al.
Published: (2004)

Effective mass and damping of submerged structures /
by: Dong, R. G.
Published: (1978)

An assessment of TRACE V5 RC1 code separator model with the Westinghouse Model Boiler 2 experiments /
by: Hillberg, S.
Published: (2010)

Natural circulation phenomena in nuclear reactor systems : presented at 1994 International Mechanical Engineering Congress and Exposition, Chicago, Illinois, November 6-11, 1994 /
Published: (1994)

Potential degradation of secondary containment.
Published: (1990)

CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident /
by: Boyd, Christopher Fred, et al.
Published: (2003)

The computer code EURDYN-1M : (release 1) for transient dynamic fluid-structure interaction.
Published: (1980)

Bulletin de la Direction des études et recherches.
Published: (1967)

Cracking in the upper shell to transition cone girth weld of a steam generator at an operating pressurized water reactor.
Published: (1982)

Post-Dryout Heat Transfer.
by: Hewitt, G. F.
Published: (2017)

Thermohydraulics of two-phase systems for industrial design and nuclear engineering /
Published: (1981)

Heat and fluid flow in water reactor safety : conference sponsored [as printed] by the Thermodynamics and Fluid Mechanics Group of the Institution of Mechanical Engineers, Manchester, 13-15 September, 1977.
Published: (1977)

Verification of RELAP5/MOD 3 with theoretical and numerical stability results on single-phase, natural circulation in a simple loop /
by: Ferreri, J. C., et al.
Published: (1999)

Safety evaluation of Westinghouse topical reports dealing with elimination of postulated pipe breaks in PWR primary main loops.
Published: (1984)

Partial bypass of shutdown cooling flow from the reactor vessel.
Published: (1996)

Transient phenomena in nuclear reactor systems : presented at the 29th National Heat Transfer Conference, Atlanta, Georgia, August 8-11, 1993 /
Published: (1993)

HPCI/RCIC high steam flow setpoints.
Published: (1982)

Overpressurization of containment of a PWR plant after a main steam line break.
Published: (1979)

Reactor cavity annulus seal ring.
Published: (1978)

Inaccurate reactor water level indication and inadvertent draindown during shutdown.
Published: (1996)

New information regarding insulation material performance and debris blockage of PWR containment sumps.
Published: (1990)

Potential impact of debris blockage on emergency recirculation during design basis accidents at pressurized-water reactors.
Published: (2004)

The "calculated" loss-of-coolant accident : a review /
by: Ybarrondo, L. J.
Published: (1972)