Published 1986 | Version v1
Book Metadata-only

Thermal-hydraulic and vibration analysis of a nuclear recirculating steam generator

Creators

  • 1. Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.

Description

This paper provides an example of a combined thermal-hydraulic and vibration analysis of a nuclear U-tube steam generator using the THIRST code to calculate the multidimensional two-phase flow field and the PIPO code to calculate the free and forced response of a specific U-tube. Several hypothetical U-bend support configurations are considered to demonstrate the effects active and inactive tube supports. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London (UK)
ISBN
0 7277 0269 6
Imprint Title
Boiler dynamics and control in nuclear power stations 3
Imprint Pagination
342 p.
Journal Page Range
p. 175-180.

Conference

Title
3. international conference on boiler dynamics and control in nuclear power stations.
Dates
21-25 Oct 1985.
Place
Harrogate (UK).

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
18032771
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLOW MODELS; HEAT TRANSFER; HYDRODYNAMICS; MECHANICAL VIBRATIONS; P CODES; PWR TYPE REACTORS; STEAM GENERATORS; T CODES; TEMPERATURE DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
Descriptors DEC
BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS