Status of Adv. Light-Water Nuclear Reactor Designs (IAEA...

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Status of Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1391)

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როგორ მოგეწონათ ეს წიგნი?

როგორი ხარისხისაა ეს ფაილი?

ჩატვირთეთ, ხარისხის შესაფასებლად

როგორი ხარისხისაა ჩატვირთული ფაილი?

კატეგორია:

Technique - Energy

წელი:

2004

ენა:

english

გვერდები:

779

ფაილი:

PDF, 20.25 MB

IPFS:

,

english, 2004

ონლაინ წაკითხვა

ხორციელდება კონვერტაციის -ში

კონვერტაციის -ში ვერ მოხერხდა

შესაძლოა დაგაინტერესოთ

— Performance of Operating, Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1245)

A L Wright; Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; et al — Primary system fission product release and transport : a state-of-the-art report to the Committee on the Safety of Nuclear Installations

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

Bengt Pershagen — Light Water Reactor Safety

G.F. Hewitt, John G. Collier — Introduction to Nuclear Power (Series in Chemical and Mechanical Engineering)

IAEA — Directory of Nuclear Reactors, Vol. 9. Power Reactors (Supplement to Vol. 4 and 7)

— Evolutionary Water-Cooled Reactors - Issues, Technologies (IAEA TECDOC-1117)

— Performance of Operating and Advanced Light-Water Reactor Designs (IAEA TECDOC-1245)

— Evaluation of Gas-Turbine Modular Helium Reactor

— Development, Design Aspects of Advanced Water Cooled Reactors (IAEA TECDOC-677)

— Accid. Anal. - Nuclear Powerplants with PWRs

— Design of Reactor Coolant Systems in Nuclear Powerplants (IAEA NS-G-1.9)

— Design, Devel Status of Small and Medium Reactor Systems (IAEA TECDOC-881)

— Integral Design Concepts - Advanced Water Cooled Reactors (IAEA TECDOC-977)

— Intro of Small, Medium Reactors in Developing Countries (IAEA TECDOC-999)

— NPR Reactor Hazards Review Vol 1 (phase 1 - production) [declassified]

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Shutdown, Low-Power Operation at Commercial Nuclear Powerplants

— Small Power, Heat - Gen. Systms - on Basis of Propulsion Reactor Tech (IAEA TECDOC-1172)

— Status of Design Concepts for Nuclear Desalinization Plants 9IAEA TECDOC-1326)

— Status, Future Devel. of Modular HTGR Technology (IAEA TECDOC-1198)

— System 80+ Standard [nucl. powerplnt] Design - Vol 05

— System 80+ Standard [nucl. powerplnt] Design - Vol 09

— System 80+ Standard [nucl. powerplnt] Design - Vol 10

— System 80+ Standard [nucl. powerplnt] Design - Vol 11

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

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

Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs — Precursors to potential severe core damage accidents : a status report

R R Fullwood; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Brookhaven National Laboratory.; et al — Integrated systems analysis of the PIUS reactor

International Atomic Energy Agency.; Argonne National Laboratory — Safety of nuclear installations : future direction

M. Ishii; S. T. Revankar; U. S. Rohatgi; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Purdue University.; Brookhaven National Laboratory.; United States. Dept. of Energy. Oakland Operations Of — MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

Max Weber; U.S. Atomic Energy Commission. Division of Reactor Development and Technology — Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972

Badulescu A. et al. — Liquid Metal Cooled Reactors: Experience in Design and Operation

Kuznetcov V. — Design Features to Achieve Defence in Depth in Small and Medium Sized Reactors

— Natural Circulation Phenomena, Modeling and Reliability of Passive Systems That Utilize Natural Circulation

— PWR Technology Cross Training Course

Haskin E., Camp L. — Perspectives on Reactor Safety

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