GSI-191 PWR sump screen blockage chemical effects tests : thermodynamic simulations / prepared by J. McMurry [and others].

Bibliographic Details
Corporate Author:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors:	McMurry, J.
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2006]
Subjects:	Pressurized water reactors > Loss of coolant. Nuclear reactors > Containment. Nuclear reactors > Cooling.
Online Access:	Connect to online resource - All users (Federal Depository Library Program Persistant URL)
Physical Description:	1 volume (various pagings) : digital, PDF file.
Format:	Government Document eBook

Similar Items

Peer review of GSI-191 chemical effects research program
by: Torres, P. A.
Published: (2006)

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)

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

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

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)

Potential for loss of post-LOCA recirculation capability due to insulation debris blockage.
Published: (1985)

Effect of aging on the PWR chemical and volume control system
by: Grove, E. J.
Published: (1995)

Resultls of chemical effects head loss tests in a simulated PWR sump pool environment.
Published: (2005)

PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report
Published: (1982)

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

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

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

Thermal-shock-resistant insulators
by: Morgan, C. S.
Published: (1981)

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

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

Evaluation of containment leak rate testing criteria
by: Dougan, J. R.
Published: (1984)

Aluminum chemistry in a prototypical post-loss-of-coolant-accident, pressurized-water-reactor containment environment
Published: (2006)

Recent operating experience on loss of reactor coolant inventory while In a shutdown condition.
Published: (1990)

Experimental measurements of pressure drop across sump screen debris beds in support of generic safety issue 191
Published: (2007)

PWR pressure vessel integrity during overcooling accidents : a parametric analysis
by: Cheverton, R. D.
Published: (1983)

Diversion of the residual heat removal pump seal cooling water flow during recirculation operation following a loss-of-coolant accident.
Published: (1989)

Loss of decay heat removal due to loss of fluid levels in reactor coolant system.
Published: (1986)

Undetected loss of reactor coolant.
Published: (1987)

Loss of emergency boration capability due to nitrogen gas intrusion.
Published: (1987)

Hydraulic transport of coating debris : a subtask of GSI-191
Published: (2006)

Technical findings related to generic issue 23 : reactor coolant pump seal failure
by: Ruger, C. J.
Published: (1989)

A method for the analysis of hydrogen and steam releases to containment during degraded core cooling accidents
by: Cybulskis, P.
Published: (1982)

Hydrogen:air:steam flammability limits and combustion characteristics in the FITS vessel
by: Marshall, Billy W. (Billy Wayne), 1957-
Published: (1986)

Drywell debris transport study : final report.
Published: (1999)

Drywell debris transport study : final report.
Published: (1999)

Regulatory analysis for the resolution of Generic issue 130 : essential service water system failures at multi-unit sites
by: Leung, V.
Published: (1991)

Applicability of LEFM to the analysis of PWR vessels under LOCA-ECC thermal shock
by: Cheverton, R. D.
Published: (1978)

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

MARK II containment program load evaluation and acceptance criteria : generic technical activity A-8
by: Anderson, C. (Clifford)
Published: (1981)

Screen penetration test report
by: Ma, Jia
Published: (2005)

Screening tests of terminal block performance in a simulated LOCA environment
by: Craft, C. M. (Charles M.)
Published: (1984)

PWR dry containment issue characterization
by: Yang, J. W. (Jiwu W.), 1934-
Published: (1990)

Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B&W plant : an application of the CSAU methodology using the RELAP5/MOD3 computer code
by: Ortiz, M. G.
Published: (1992)

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)

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