Transient thermal-hydraulics in vessel and piping systems presented at the 1989 ASME Pressure Vessels and Piping Conference--JSME co-sponsorship, Honolulu, Hawaii, July 23-27, 1989 by Pressure Vessels and Piping Conference (1989 Honolulu, Hawaii)

Cover of: Transient thermal-hydraulics in vessel and piping systems | Pressure Vessels and Piping Conference (1989 Honolulu, Hawaii)

Published by American Society of Mechanical Engineers in New York, N.Y .

Written in English

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  • Fluid dynamics -- Congresses.,
  • Pressure vessels -- Fluid dynamics -- Congresses.,
  • Piping -- Fluid dynamics -- Congresses.,
  • Heat -- Transmission -- Congresses.

Edition Notes

Includes bibliographical references.

Book details

Statementedited by Y.W. Shin, F.J. Moody.
SeriesPVP ;, vol. 156, PVP (Series) ;, vol. 156.
ContributionsShin, Yong W., Moody, F. J., Nihon Kikai Gakkai.
LC ClassificationsTA357 .A86 1989a
The Physical Object
Paginationv, 126 p. :
Number of Pages126
ID Numbers
Open LibraryOL2230628M
ISBN 100791803120
LC Control Number89084543

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Transient Thermal Hydraulics in Vessel and Piping Systems (PVP) [Y. Shin, F. Moody] on *FREE* shipping on qualifying offers. Get this from a library. Transient thermal-hydraulics in vessel and piping systems: presented at the ASME Pressure Vessels and Piping Conference--JSME co-sponsorship, Honolulu, Hawaii, July[Yong W Shin; F J Moody; Nihon Kikai Gakkai.;].

Get this from a library. Transient thermal hydraulics and resulting loads on vessel and piping systems, presented at the Pressure Vessels and Piping Conference, Nashville, Tennessee, June[F J Moody; Yong W Shin; J D Colton; American Society of Mechanical Engineers.

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Fenton, R.M., and Griffith, P. () The forces at a pipe bend due to the clearing of water trapped upstream, Transient Thermal Hydraulics and Resulting Loads on Vessel and Piping Systems, American Society of Mechanical Engineers PVP Vol.New York, pp.

59– Google ScholarCited by: 7. Finally, a transient neutronics module is often integrated into the code to model the coupling between the core neutronics and the core thermal-hydraulics during certain events (e.g.

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59–Cited by: 9. Analysis of Liquid Slug Motion in a Voided Line J. Yang, J. Yang ,” Transient Thermal Hydraulics and Resulting Loads on Vessel and Piping Systems, ASME PVP-Vol.New York, NY, pp. Cited by: 5. Integrity of the blowdown piping systems in a nuclear power plant - findings and consequences SMVolume II, Division F, Pressure Vessels and Piping, page 85 - 96 E-Mail: [email protected] @article{osti_, title = {EBR-II in-vessel natural-circulation analysis}, author = {Baumann, W L and Domanus, H M and Mohr, D and Sha, W T and Schmitt, R C and Sullivan, J E}, abstractNote = {The in-vessel thermal-hydraulic analysis of the EBR-II Pool Reactor for Transient Test No.

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Everstine, Applications of Linear Algebra (ApSc). CHAPTER 7 THERMAL-HYDRAULIC ANALYSIS The coolant in the pressure tube of the CANDU nuclear reactor core removes the thermal energy produced in the nuclear fuel.

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Flow behaviour affecting the wall thinning of the piping due to a Flow Accelerated Corrosion (FAC) at the pressure boundary of nuclear reactor systems Subcooled boiling phenomena [8]; Severe accident–related issues such as the thermal loads on the reactor vessel due to a core melt and hydrogen behaviour in a containment [9].

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TABLE Of CONTENTS (Coatinued). Sstilan lilla Eage ASME Section III Fatigue Usage factor Evaluation " Hothodology Fatigue Usage Factors Fatigue Due to Thermal Striping Fatigue Usage Results ~ Analysis Summary References Appendix A List of Computer Programs A-1 Appendix B USNRC Bulletin B-1 Appendix C Transient Development.

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