Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983

Technical Report · Sun Apr 01 00:00:00 EST 1984

OSTI ID:6853815

This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6853815
• Report Number(s): NUREG/CR-3689-Vol.1; ANL-83-85-Vol.1; ON: DE84013342
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR MATERIALS
REACTOR SAFETY
PWR TYPE REACTORS
RESEARCH PROGRAMS
COMPUTER CALCULATIONS
CRACKS
EMBRITTLEMENT
FISSION PRODUCT RELEASE
FUEL CANS
FUEL-CLADDING INTERACTIONS
PHYSICAL RADIATION EFFECTS
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
STAINLESS STEELS
STRESS CORROSION
ZIRCALOY
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
RADIATION EFFECTS
REACTORS
SAFETY
STEELS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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