Normal Accidents

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Normal Accidents

Charles Perrow

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फ़ाइल की गुणवत्ता क्या है?

पुस्तक की गुणवत्ता का मूल्यांकन करने के लिए यह पुस्तक डाउनलोड करें

डाउनलोड की गई फ़ाइलों की गुणवत्ता क्या है?

Discusses the pros and cons of high-risk technologies, explains how to reduce the possibilities for catastrophic accidents, and analyzes the causes of specific industrial accidents

श्रेणियाँ:

साल:

1984

संस्करण:

1st

प्रकाशन:

Basic Books

भाषा:

english

पृष्ठ:

386

ISBN 10:

046505143X

ISBN 13:

9780465051434

फ़ाइल:

PDF, 20.56 MB

IPFS:

,

english, 1984

ऑनलाइन पढ़ें

डाउनलोड करें (pdf, 20.56 MB)

में रूपांतरण जारी है

में रूपांतरण विफल रहा

आप के लिए दिलचस्प हो सकता है

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Sidney Dekker — Foundations of Safety Science: A Century of Understanding Accidents and Disasters

Strauch, Barry — Investigating Human Error: Incidents, Accidents, and Complex Systems, Second Edition

James Reason — Managing the Risks of Organizational Accidents

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Bengt Pershagen — Light Water Reactor Safety

Bonnie A. Osif, Anthony J. Baratta, Thomas W. Conkling — TMI 25 Years Later: The Three Mile Island Nuclear Power Plant Accident and Its Impact

Gianni Petrangeli — Nuclear Safety

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

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

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

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

— Accid. Anal. - Nuclear Powerplants with PHWRs

— Accid. Anal. - Nuclear Powerplants with PWRs

— Aging Assessment - Westinghouse PWR, GE BWR Containment Isol Fns

— 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)

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

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— Water Reactor Safety Info Meeting Vol 1 [21st, transactions]

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D A Conley; Jerald L Edson; C F Fineman; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering — Aging study of boiling water reactor high pressure injection systems

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

J C Cleveland; J C Conklin; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Oak Ridge National Laboratory — High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

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— PWR Technology Cross Training Course

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

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