Published June 1981 | Version v1
Report Restricted

Early response of pressurized hot water in a pipe to a sudden break. Final report

Creators

Description

Experimental and analytic studies that explain the details of early pressure variations during rapid depressurization in water-cooled reactors are presented as a means of assessing sudden break consequences in a coolant pipe. The report includes (1) a description of the experiment, (2) an analysis of the new bubble growth law for thermally controlled growth of vapor bubbles in an exponentially-varying pressure field, and (3) a review of previous studies and additional observations of blowdown behavior

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A10/MF A01.

Files

Restricted

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

Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
215 p.
Report number
EPRI-NP--1867

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12632458
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
BLOWDOWN; BWR TYPE REACTORS; DEPRESSURIZATION; HYDRAULICS; LOSS OF COOLANT; PIPES; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SIMULATION
Descriptors DEC
ACCIDENTS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS