Modeling of reactor components using FIDAP : a finite element computer code /

Potential for loss of shutdown cooling while at low reactor coolant levels.
Published: (1990)

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

Natural circulation phenomena and modelling for advanced water cooled reactors.
Published: (2012)

Loss of reactor coolant inventory and associated potential for loss of emergency mitigation functions while in a shutdown condition.
Published: (1998)

Possible sudden loss of RCS inventory during low coolant level operation.
Published: (1988)

Loss of decay heat removal--10 CFR 50.54(f).
Published: (1988)

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

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

GSI-191 PWR sump screen blockage chemical effects tests : thermodynamic simulations /
Published: (2006)

Potential for common-mode failure of high pressure safety injection pumps or release of reactor coolant outside containment during a loss-of-coolant accident.
Published: (1990)

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

Potential overpressurization of the component cooling water system.
Published: (1989)

Thermal analysis of pressurized water reactors /
by: Tong, L. S. (Long-sun), 1915-, et al.
Published: (1979)

Reactor cavity annulus seal ring.
Published: (1978)

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

Potential for degradation of the emergency core cooling system and the containment spray system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment.
Published: (1998)

The nuclear fuel of pressurized water reactors and fast neutron reactors : design and behaviour /
Published: (1999)

RHR valve misalignment causes degradation of ECCS in PWRS.
Published: (1987)

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

Resolution of generic issue 79, "Unanalyzed reactor vessel (PWR) thermal stress during natural convection cooldown".
Published: (1992)

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data /
by: Odar, Fuat
Published: (2001)

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

Circumferential cracking in the stainless steel pressurized heater sleeves of pressurized water reactors.
Published: (2006)

Development, implementation, and assessment of specific closure laws for inverted-annular film-boiling in a two-fluid model /
by: Cachard, François de
Published: (1996)

Assessment of RELAP5/MOD2 against ECN-reflood experiments /
by: Woudstra, A., et al.
Published: (1993)

Water coolant technology of power reactors /
by: Cohen, P. (Paul)
Published: (1980)

Water coolant technology of power reactors.
by: Cohen, P. (Paul)
Published: (1969)

Foreign experience regarding boron dilution.
Published: (1991)

Design of the reactor pressure vessel support system.
Published: (1978)

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

Actuation of ECCS in the recirculation mode while in hot shutdown.
Published: (1980)

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

Assessment of RELAP5/MOD2 against a natural circulation experiment in nuclear power plant Borssele /
by: Winters, L.
Published: (1993)

Guidebook to light water reactor safety analysis /
Published: (1985)

Supercritcal-water-cooled reactor [SCWR].
Published: (2007)

Loose parts in the secondary side of steam generators at pressurized water reactors.
Published: (1983)