Light-water-reactor safety research program. Quarterly progress report, July--September 1975

Technical Report · Wed Jan 01 00:00:00 EST 1975

DOI:https://doi.org/10.2172/7290934· OSTI ID:7290934

Progress is summarized in the following research and development areas: (1) loss-of-coolant accident research; heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; and (3) mechanical properties of Zircaloy containing oxygen. Also included is an appendix on Kinetics of Fission Gas and Volatile Fission-product Behavior under Transient Conditions in LWR Fuel.

• Research Organization: Argonne National Lab., Ill. (USA)
• OSTI ID: 7290934
• Report Number(s): ANL-75-72; TRN: 76-013115
• 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
BWR TYPE REACTORS
REACTOR SAFETY
PWR TYPE REACTORS
RESEARCH PROGRAMS
ZIRCALOY 2
MECHANICAL PROPERTIES
ZIRCALOY 4
BLOWDOWN
CRITICAL HEAT FLUX
FISSION PRODUCT RELEASE
FLUID FLOW
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MELTDOWN
OXIDATION
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
ENERGY TRANSFER
FLUID MECHANICS
HEAT FLUX
IRON ADDITIONS
IRON ALLOYS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
TIN ALLOYS
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
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties