Published January 1980 | Version v1
Report Restricted

Study of the state of design for pipe whip. Final report

Creators

Description

Design methods and parameters are described which are addressed when considering consequences of a postulated pipe rupture event in a nuclear plant design. Parameters discussed are break opening time and size, resultant blowdown characteristics of the effluent from the broken pipe, jet reaction and impingement loading, pipe motion, and pipe impact loading on steel and concrete structures. The impact the various parameters have on overall plant designs and conservatisms inherent in each consideration are evaluated in a qualitative nature. Finally, recommendations are provided for each parameter discussed for further evaluation and study

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.

Files

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Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
53 p.
Report number
EPRI-NP--1320

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11552390
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; FAILURES; IMPACT SHOCK; LOSS OF COOLANT; MOTION; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; STRESSES; SUPPORTS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; MECHANICAL STRUCTURES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS