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Title: Heat transfer and fluid flow in nuclear systems

Abstract

The present publication is an attempt to provide a bridge between fundamental principles and current design practice. It is intended to serve the need of: engineers, scientists and graduate students active in thermal and hydraulics problems and to those interested to keep abreast of the field. The text is addressed to readers with previous knowledge in heat transfer and fluid flow equvalent to a one year university graduate course in that field. Because of the high degree of specialization covered in the six chapters of the book, individual authors of international reputation and active in their respective area of specialization were selected to contribute their knowledge. Each of the six chapters or sub-chapters are self-contained. They are followed by problem sets to enable the reader to check his level of comprehension of the material presented. The nuclear systems covered in separate chapters include: the pressurized and boiling water reactors (PWR, BWR), the helium cooled high temperature reactors (HTGR and HTR), the breeders helium cooled (GCFR) and sodium cooled (LMFBR). In addition the heat-exchangers and steam generators commonly associated with the above systems are covered in Chapter 6.

Authors:
 [1]
  1. ed.
Publication Date:
OSTI Identifier:
5535051
Resource Type:
Book
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; BWR TYPE REACTORS; FLUID FLOW; HEAT TRANSFER; GCFR TYPE REACTORS; STEAM GENERATORS; HTGR TYPE REACTORS; LMFBR TYPE REACTORS; HEAT EXCHANGERS; PWR TYPE REACTORS; REACTOR CORES; DESIGN; BOILERS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210000* - Nuclear Power Plants; 420400 - Engineering- Heat Transfer & Fluid Flow

Citation Formats

Fenech, H. Heat transfer and fluid flow in nuclear systems. United States: N. p., 1981. Web.
Fenech, H. Heat transfer and fluid flow in nuclear systems. United States.
Fenech, H. Thu . "Heat transfer and fluid flow in nuclear systems". United States.
@article{osti_5535051,
title = {Heat transfer and fluid flow in nuclear systems},
author = {Fenech, H},
abstractNote = {The present publication is an attempt to provide a bridge between fundamental principles and current design practice. It is intended to serve the need of: engineers, scientists and graduate students active in thermal and hydraulics problems and to those interested to keep abreast of the field. The text is addressed to readers with previous knowledge in heat transfer and fluid flow equvalent to a one year university graduate course in that field. Because of the high degree of specialization covered in the six chapters of the book, individual authors of international reputation and active in their respective area of specialization were selected to contribute their knowledge. Each of the six chapters or sub-chapters are self-contained. They are followed by problem sets to enable the reader to check his level of comprehension of the material presented. The nuclear systems covered in separate chapters include: the pressurized and boiling water reactors (PWR, BWR), the helium cooled high temperature reactors (HTGR and HTR), the breeders helium cooled (GCFR) and sodium cooled (LMFBR). In addition the heat-exchangers and steam generators commonly associated with the above systems are covered in Chapter 6.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {1}
}

Book:
Other availability
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