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Proc. 7th meeting on nuclear reactor thermal-hydraulics NURETH-7

Block, Feiner. (eds.)

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الفئات:

المجلد:

Vol.2.

عام:

1995

اللغة:

english

الصفحات:

797

ISBN 10:

9517638302

ISBN 13:

9789517638302

ملف:

DJVU, 9.05 MB

IPFS:

,

english, 1995

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Block, Feiner. (eds.) — Proc. 7th meeting on nuclear reactor thermal-hydraulics NURETH-7 (1995)

Block, Feiner. (eds.) — Proc. 7th meeting on nuclear reactor thermal-hydraulics NURETH-7

Block, Feiner. (eds.) — Proc. 7th meeting on nuclear reactor thermal-hydraulics NURETH-7

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— Progress in Safety Systems for Advanced Water-Cooled Reactors (IAEA TECDOC-872)

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— LMFR Core and Heat Exch. Thermohydraulic Design - USSR Approaches (IAEA TECDOC-1060)

— Natural Circulation in Water-Cooled Nuclear Powerplants

— Tech Feas, Reliability of Passive Safety Systems for Nucl Powerplants (IAEA TECDOC-920)

— Theoretical, Exper. Studies of Heavy Liquid Metal Thermal Hydraulics (IAEA TECDOC 1520)

— Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

— Water Reactor Safety Info Meeting Vol 2 [20th, Transactions]

— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

International Atomic Energy Agency.; Agence Internationale de l'Energie Atomique — Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors : proceedings of a Technical Committee meeting held in Villigen, Switzerland, 14-17 September 1998

International Atomic Energy Agency — LMFR core thermohydraulics : status and prospects

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; OECD Nuclear Energy Agency — Proceedings of the CSNI Specialists Meeting on Fuel-Coolant Interactions : held in Santa Barbara, California, USA, January 5-8, 1993

中国核能动力学会反应堆热工流体专业委员会空泡物理和自然循环国家级重点实验室 — 核反应堆热工词典

Pioro I. — Boiling and Condensation Advances 2024

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Sittmann I. — Inside-pipe heat transfer coefficient

Donald Quentin Kern — Process heat transfer

Kern — Process Heat Transfer

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Unknown Author — First U.K. National Conference on Heat Transfer. Volume 1.86

Jun Wang, Xin Li, Chris Allison, Judy Hohorst — Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application

Sander L. Gilman, David J. Parent — Convective Boiling and Condensation

Vladimir B. Khabensky (Author); Vladimir Antonovich Gerliga (Author) — Coolant Flow Instabilities in Power Equipment

Pradip Saha — Nuclear Reactor Thermal-Hydraulics: Past, Present and Future

Richard T., Jr. Lahey, F. J. Moody — The Thermal-Hydraulics of a Boiling Water Nuclear Reactor

L. S. Tong, Joel Weisman — Thermal Analysis of Pressurized Water Reactors

J. Brian Knowles — Nuclear Electric Power: Safety, Operation, and Control Aspects

Robert E. Masterson (Author) — Nuclear Reactor Thermal Hydraulics-An Introduction to Nuclear Heat Transfer and Fluid Flow

Tang, Yu S.; Tong, Long-sun — Boiling Heat Transfer and Two-Phase Flow

Mujid S. Kazimi; Neil E. Todreas — Nuclear Systems, Vol. 1: Thermal Hydraulic Fundamentals

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