Published March 1980 | Version v1
Report Restricted

EPRI workshop proceedings: basic two-phase flow modeling in reactor safety and performance

Description

The safety and performance of nuclear reactors involves many problems related to two-phase flow and heat transfer. The two main objectives of this workshop were to update and provide a definitive review of various approaches to two-phase flow and heat transfer modelling and attempt to identify or sense future directions. The sessions included two or three rather short keynote presentations followed by discussions. These progressed from basic modelling and phenomena, on to complex system codes. The participants included mostly specialists representing not only various approaches but also different interests: theoreticians, experimentalists, code developers and users, people from utilities, industries, universities, national laboratories and government

Availability note (English)

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

Files

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Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
211 p.
Report number
EPRI-WS--78-143(Vol.1)

Conference

Title
Conference on basis two-phase flow modeling in reactor safety and performance.
Dates
2 Mar 1979.
Place
Tampa, FL, USA.

Optional Information

Secondary number(s)
CONF-790326--(Vol.1).