Materials Science Division light-water-reactor safety research program. Quarterly progress report, January-March 1982

Technical Report · Fri Oct 01 00:00:00 EDT 1982

OSTI ID:6756673

Shack, W J; Rest, J; Kassner, T F

Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission product release; and clad properties for code verification.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6756673
• Report Number(s): NUREG/CR-2970-Vol.1; ANL-82-41-Vol.1; ON: DE83001531
• 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 MATERIALS
PWR TYPE REACTORS
FATIGUE
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-304
ZIRCALOY
CRACKS
FISSION PRODUCT RELEASE
FUEL CANS
LEAK TESTING
PIPES
REACTOR SAFETY
TRANSIENTS
ULTRASONIC TESTING
ACOUSTIC TESTING
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
NICKEL ALLOYS
NONDESTRUCTIVE TESTING
RADIATION EFFECTS
REACTORS
SAFETY
STAINLESS STEELS
STEELS
TESTING
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
360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects