Published 1996 | Version v1
Book Metadata-only

A simplified model for nuclear steam generator

Creators

  • 1. Nuclear Power Corporation of India Ltd., Bombay (India). Primary Heat Transport Section
  • 2. Indian Inst. of Tech., Bombay (India). Dept. of Mechanical Engineering

Description

In this work a simplified model is developed for the simulation of the thermal-hydraulic parameters of U-tube steam generators (UTSG) used in nuclear power plants. These are arrived at by solving steady, one-dimensional area averaged conservation equations of mass momentum and energy using finite difference method. The results obtained for the steam generators used in Indian nuclear power station compared well with those obtained by three dimensional HELIOS computer code. Further, the results obtained for a typical Westinghouse steam generator compare favourably with the experimental results. (author). 8 refs., 8 figs., 5 tabs

Part of:
Heat and mass transfer 95

Additional details

Publishing Information

Publisher
Tata McGraw-Hill Publishing Company Limited.
Imprint Place
New Delhi (India)
ISBN
0-07-462307-9
Imprint Title
Heat and mass transfer 95
Imprint Pagination
975 p.
Journal Page Range
p. 639-644.

Conference

Title
2. ISHMT-ASME heat and mass transfer conference; 13. national heat and mass transfer conference.
Dates
28-30 Dec 1995.
Place
Surathkal (India).

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
27075605
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FINITE DIFFERENCE METHOD; HEAT TRANSFER; HYDRAULICS; NARORA-1 REACTOR; NARORA-2 REACTOR; PERFORMANCE TESTING; S CODES; STEADY-STATE CONDITIONS; STEAM GENERATORS; TRICASTIN-1 REACTOR
Descriptors DEC
BOILERS; CALCULATION METHODS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ITERATIVE METHODS; NATURAL URANIUM REACTORS; NUMERICAL SOLUTION; PHWR TYPE REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information