Light-Water-Reactor safety research program. Quarterly progress report, January--March 1977

Technical Report · Wed Jun 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/7095522· OSTI ID:7095522

The report summarizes the Argonne National Laboratory work performed during January, February, and March 1977 on water-reactor-safety 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: 7095522
• Report Number(s): ANL-77-34
• 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
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
ZIRCALOY 4
MECHANICAL PROPERTIES
DEFORMATION
EMBRITTLEMENT
EXPLOSIONS
FISSION PRODUCT RELEASE
FUEL CANS
MOLTEN METAL-WATER REACTIONS
OXIDATION
REACTOR SAFETY
RESEARCH PROGRAMS
RUPTURES
STEAM
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
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