Published 1993 | Version v1
Book

Two-phase flow modeling for next generation nuclear power plant simulators

  • 1. Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Nuclear Engineering and Engineering Physics
  • 2. S3 Technologies, Columbia, MD (United States)

Description

This paper is concerned with the analysis of various modeling and numerical aspects of two-phase flow and heat transfer phenomena under transient and accident conditions, which are important for the development of real-time simulators of nuclear power plants. Issues discussed include, among others, the scope of modeled phenomena, modeling concepts, numerical methods, and factors affecting the accuracy of calculations. General considerations are complemented with quantitative examples illustrating specific questions

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0636-7
Imprint Title
2nd ASME-JSME international conference on nuclear engineering -- 1993
Imprint Pagination
770 p.
Journal Page Range
p. 201-207.

Conference

Title
2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
Dates
21-24 Mar 1993.
Place
San Francisco, CA (United States).

Optional Information

Secondary number(s)
CONF-930352--.