Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, January--March 1976

Technical Report · Tue Jun 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7176982· OSTI ID:7176982

Zane, J. O.; Farman, R. F.; Hanson, D. J.; Peterson, A. C.; Ybarrondo, L. J.; Berta, V. T.; Naff, S. A.; Crocker, J. G.; Martinson, Z. R.; Smolik, G. R.; Cawood, G. W.; Quapp, W. J.; Ramsthaler, J. H.; Ransom, V. H.; Scofield, M. P.; Dearien, J. A.; Bohn, M. P.; Burnham, B. W.; James, S. W.; Lee, W. H. ; Lime, J. F.; Nalezny, C. L.; MacDonald, P. E.; Thompson, L. B.; Domenico, W. F.; Rice, R. E.; Hendrix, C. E.; Davis, C. B.

Light water reactor sfaety research performed January through March 1976 is summarized. Results of the Semiscale Mod-1 blowdown heat transfer test series relating to those phenomena that influence core fluid and heat transfer effects are analyzed, and preliminary analyses of the recently completed reflood heat transfer test series are summarized for the forced and gravity feed reflood tests. The first nonnuclear LOCE in the LOFT program was successfully completed and preliminary results are presented. Preliminary results are given for the PCM 8-1 RF Test, the PCM-2A Test, and the Irradiation Effects Scoping Test 2 in the Thermal Fuel Behavior Program. Model development and verification efforts reported in the Reactor Behavior Program include checkout of RELAP4/MOD5 Update 1, development of a new hydrodynamic model for two-phase separated flows, development of the RACHET code to assess the assumptions in current fuel behavior codes of uniform stress and strain in the cladding, modifications of the containment code BEACON, analysis of results from the Halden Assembly IFA-429 helium sorption experiment, development of correlations for the thermal conductivity of UO/sub 2/ and (U,Pu)O/sub 2/, and evaluation of RALAP4 through comparison of calculated results with data from the GE Blowdown Heat Transfer and Semiscale experiments.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• OSTI ID: 7176982
• Report Number(s): ANCR-NUREG-1315
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
360204 -- Ceramics
Cermets
& Refractories-- Physical Properties
ACCIDENTS
ACTINIDE COMPOUNDS
BLOWDOWN
BWR TYPE REACTORS
CHALCOGENIDES
COMPUTER CALCULATIONS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
OPERATION
OXIDES
OXYGEN COMPOUNDS
PBF REACTOR
PERFORMANCE
PHYSICAL PROPERTIES
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE GRADIENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSURANIUM COMPOUNDS
TWO-PHASE FLOW
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS