Published 1977 | Version v1
Book Metadata-only

Thermal hydraulic analysis of Rajasthan Nuclear Power Station primary circuits

Creators

  • 1. Bhabha Atomic Research Centre, Bombay (India)

Description

This paper presents the complete thermal hydraulic analysis of a pressurised heavy water nuclear reactor system by using principles developed earlier for a BWR system. The code calculates the exact thermodynamic properties at any point in the reactor hydraulic circuit and determines the stable operating point on the pump characteristics. (auth.)

Additional details

Publishing Information

Publisher
Sarita Prakashan.
Imprint Place
Meerut
Imprint Title
Proceedings of fourth national heat and mass transfer conference 1977 [held at Roorkee]
Journal Page Range
p. 771-779.

Conference

Title
4. national heat and mass transfer conference.
Dates
21 - 23 Nov 1977.
Place
Roorkee, India.

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
12589066
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; HYDRAULICS; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; PUMPS; RAJASTHAN-1 REACTOR; RAJASTHAN-2 REACTOR; THERMODYNAMICS
Descriptors DEC
CANDU TYPE REACTORS; COOLING SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS