Published June 1975 | Version v1
Report

Theoretical investigation of reactor primary coolant pipe, welds and fittings. Technical report

Description

A dynamic analytical model for a running axial crack in a cylindrical shell was developed and used to study the propagation of cracks due to a steady initial pressure and cracks arising during instantaneous pressurization. A thermal hydraulic two phase depressurization model which permits depressurization to occur by leakage through an axial crack was also developed to permit the study of axial running cracks subjected to the varying pressure caused by leakage. Stress intensity factors for surface cracks in pressurized and thermally shocked cylinders were also derived

Additional details

Additional titles

Augmented title (English)
PWR

Publishing Information

Imprint Pagination
170 p.
Report number
PB--244431

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7269087
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CRACKS; LEAKS; MATHEMATICAL MODELS; PIPE FITTINGS; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STRESSES; THERMAL STRESSES; WELDED JOINTS
Descriptors DEC
COOLING SYSTEMS; JOINTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Available from NTIS. $6.25.