Reactor cavity annulus seal ring.

Overexposure of diver in pressurized water reactor (PWR) refueling cavity.
Published: (1984)

Stream/water interaction in a scaled pressurized water reactor downcomer annulus /
by: Crowley, Christopher J.
Published: (1974)

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

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)

Reactor cavity seal ring generic issue.
Published: (1979)

An approach for estimating the frequencies of various containment failure modes and bypass events : final report /
Published: (2004)

An approach for estimating the frequencies of various containment failure modes and bypass events : draft report for comment /
by: Pratt, W. T. (William T.)
Published: (2003)

Hydrogen:air:steam flammability limits and combustion characteristics in the FITS vessel /
by: Marshall, Billy W.
Published: (1986)

GSI-191 : experimental studies of loss-of-coolant-accident-generated debris accumulation and head loss with emphasis on the effects of calcium silicate insulation /
Published: (2005)

Corrosion rate measurements and chemical speciation of corrosion products using thermodynamic modeling of debris components to support GSI-191 /
by: Jain, V.
Published: (2005)

Safety/relief valve quencher loads : evaluation for BWR Mark II and III containments.
Published: (1982)

Errors in main steam line break analyses for determining containment parameters.
Published: (1991)

The Role of nuclear reactor containment in severe accidents : report /
Published: (1989)

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

Containment integrated leak rate tests.
Published: (1985)

Vacuum relief system for boiling water reactor Mark I and Mark II containments.
Published: (1985)

Depressurization of reactor coolant systems in pressurized-water reactors.
Published: (1987)

Isolation of reactor coolant system from low-pressure systems outside containment.
Published: (1984)

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

Two events involving unauthorized entries into PWR reactor cavities.
Published: (1984)

Potential degradation of secondary containment.
Published: (1990)

Degraded coatings and corrosion of steel containment vessels.
Published: (1989)

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

Final results of the hydrogen igniter experimental program /
by: Lowry, W. E., et al.
Published: (1982)

Inter-system discharge of reactor coolant.
Published: (1990)

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

Effects of degradation on the severe accident consequences for a PWR plant with a reinforced concrete containment vessel /
by: Petti, J. P.
Published: (2013)

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

Overpressurization test of a 1:4-scale prestressed concrete containment vessel model /
Published: (2003)

Inadvertent containment spray and reactor vessel draindown at Millstone Unit 1.
Published: (1994)

Liner plate corrosion in concrete containments.
Published: (1997)

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

Recent discovery of a phenomenon not previously considered in the design of secondary containment pressure control.
Published: (1988)

Modeling of reactor components using FIDAP : a finite element computer code /
by: Gangadharan, Anand, 1963-
Published: (1989)

Overexposures in PWR cavities.
Published: (1982)

IEB 80-17 supplement 1 failure of control rods to insert during a scram at a BWR.
Published: (1980)