Sumbangan 15 September 2024 – 1 Oktober 2024 Tentang pengumpulan dana

Nuclear power plant design characteristics : structure of...

Main
Engineering
Nuclear power plant design...

Nuclear power plant design characteristics : structure of nuclear power plant design characteristics in the IAEA Power Reactor Information System (PRIS)

J Mandula, International Atomic Energy Agency

0 / 0

Sukakah Anda buku ini?

Bagaimana kualitas file yang diunduh?

Unduh buku untuk menilai kualitasnya

Bagaimana kualitas file yang diunduh?

Kategori:

Tahun:

2007

Penerbit:

International Atomic Energy Agency

Bahasa:

english

Halaman:

40

ISBN 10:

9201025076

ISBN 13:

9789201025074

Nama seri:

IAEA-TECDOC, 1544

File:

PDF, 562 KB

IPFS:

,

english, 2007

Membaca daring

Pengubahan menjadi sedang diproses

Pengubahan menjadi gagal

Mungkin Anda tertarik

Pablo Rubiolo, Principal Investigator; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Westinghouse Electric Corporation.; United States. Dept. of Energy. Oakland Operations Office.; United States. Dept. of Energy. Office of Scientific a — Novel, Integrated Reactor

Ian Hore-Lacy — Uranium for Nuclear Power: Resources, Mining and Transformation to Fuel

Committee on Application of Digital Instrumentation and Control Systems to Nuclear Power Plant Operations and Safety, National Research Council — Digital Instrumentation and Control Systems in Nuclear Power Plants: Safety and Reliability Issues

Harrer J.M., Beckerley J.G. — Nuclear Power Reactor Instrumentation Systems Handbook Volume 2

Dr.?Ing. habil. Rudiger Meiswinkel, Dr.?Ing. Julian Meyer, Prof. Dr.?Ing. Jurgen Schnell(auth.), Konrad Bergmeister, Frank Fingerloos, Johann?Dietrich Worner(eds.) — Design and Construction of Nuclear Power Plants

Iaea — Radiation Protection in the Design of Radiotherapy Facilities

D Delves; International Atomic Energy Agency — IAEA safety glossary : terminology used in nuclear safety and radiation protection

International Atomic Energy Agency.; OECD Nuclear Energy Agency — Management of spent fuel from nuclear power reactors : proceedings of an international conference on spent fuel from nuclear power reactors

International Atomic Energy Agency — Characterization and testing of materials for nuclear reactors : proceedings of a technical meeting held in Vienna, May 29[U+2013]June 2, 2006

International Atomic Energy Agency — Managing the first nuclear power plant project

INTERNATIONAL ATOMIC ENERGY AGENCY — Uranium Production and Raw Materials for the Nuclear Fuel Cycle-Supply and Demand Economics the Environment and Energy Security

International Atomic Energy Agency — Design aspects of radiation protection for nuclear power plants : a safety guide

Bengt Pershagen — Light Water Reactor Safety

Janet Wood — Nuclear Power (IET Power and Energy)

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

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

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

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

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

— Accid. Anal. - Nuclear Powerplants with PHWRs

— 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)

— Generic Safety Issues for Nucl Powerplants with LWRs (IAEA TECDOC-1044)

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

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

— Small, Med Sized Nuclear Reactor Designs - Design Feats, Safety Approaches (IAEA TECDOC-1451)

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

— 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 10

— System 80+ Standard [nucl. powerplnt] Design - Vol 12

— System 80+ Standard [nucl. powerplnt] Design - Vol 18

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

— Thermohydraulics of Emergency Core Cooling in LWRs (csni89-161)

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

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

International Atomic Energy Agency — Unusual occurrences during LMFR operation

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

Colin Tucker — How to Drive a Nuclear Reactor

Istilah kunci