Light-Water-Reactor Safety Research Program: quarterly report, July--September 1976

Technical Report · Wed Dec 01 00:00:00 EST 1976

DOI:https://doi.org/10.2172/7116800· OSTI ID:7116800

The report summarizes the Argonne National Laboratory work performed during July, August, and September 1976 on water-reactor-safety heat-transfer and flow problems. The following research and development areas are covered: (1) loss-of-coolant accident research: heat transfer and fluid dynamics; (2) transient fuel response and fission-product release program; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: US Energy Research and Development Administration (ERDA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 7116800
• Report Number(s): ANL-76-121
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ALUMINIUM
MOLTEN METAL-WATER REACTIONS
BWR TYPE REACTORS
LOSS OF COOLANT
FUEL CANS
DEFORMATION
FUEL PELLETS
FISSION PRODUCT RELEASE
FLUID FLOW
HEAT TRANSFER
PWR TYPE REACTORS
URANIUM DIOXIDE
RADIONUCLIDE MIGRATION
ZIRCALOY 2
MECHANICAL PROPERTIES
OXIDATION
ZIRCALOY 4
BLOWDOWN
CRITICAL HEAT FLUX
DIFFUSION
ENERGY YIELD
EXPLOSIONS
FISSION PRODUCTS
MICROSTRUCTURE
POWER-COOLING-MISMATCH ACCIDENTS
RESEARCH PROGRAMS
SIMULATION
STEAM
WATER
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CRYSTAL STRUCTURE
ELEMENTS
ENERGY TRANSFER
ENVIRONMENTAL TRANSPORT
HEAT FLUX
HYDROGEN COMPOUNDS
IRON ADDITIONS
IRON ALLOYS
ISOTOPES
MASS TRANSFER
METALS
OXIDES
OXYGEN COMPOUNDS
PELLETS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties
360206 - Ceramics
Cermets
& Refractories- Radiation Effects