Published August 1973 | Version v1
Report Restricted

Reactor primary coolant system pipe rupture study. Progress report No. 29, January--June 1973

Creators

Description

no abstract available

Availability note (English)

MF available from INIS under the Report Number.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
BWR

Publishing Information

Imprint Pagination
83 p.
Report number
GEAP--10207-29

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
5110120
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Progress Report
Descriptors DEI
BWR TYPE REACTORS; CARBON STEELS; CRACKS; FATIGUE; INCONEL 600; MATERIALS TESTING; PIPE JOINTS; PIPES; PRIMARY COOLANT CIRCUITS; RELIABILITY; RUPTURES; STAINLESS STEEL-304; STAINLESS STEEL-304L; STRAINS; STRESSES
Descriptors DEC
ALLOYS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; FAILURES; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS