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Normal Accidents

Charles Perrow

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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

سب زمرہ:

سال:

1984

اشاعت:

1st

ناشر کتب:

Basic Books

زبان:

english

صفحات:

386

ISBN 10:

046505143X

ISBN 13:

9780465051434

فائل:

PDF, 20.56 MB

IPFS:

,

english, 1984

آن لائن پڑھیں

ڈاؤن لوڈ کریں (pdf, 20.56 MB)

میں تبدیلی جاری ہے۔

میں تبدیلی ناکام ہو گئی۔

آپ کو دلچسپی ہوسکتی ہے

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Charles Perrow — The Next Catastrophe: Reducing Our Vulnerabilities to Natural, Industrial, and Terrorist Disasters

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Jean-Christophe Le Coze — Post Normal Accident: Revisiting Perrow's Classic

Charles Perrow — Complex Organizations : A Critical Essay (Third Edition)

Charles Perrow — Normal accidents : living with high-risk technologies

Karl E. Weick, Kathleen M. Sutcliffe — Managing the Unexpected.

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

（美）查尔斯·佩罗（Charles Perrow） — 高风险技术与“正常”事故

Charles Perrow — Organizing America: Wealth, Power, and the Origins of Corporate Capitalism

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)

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

— System 80+ Standard [nucl. powerplnt] Design - Vol 07

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

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

— Water Reactor Safety Info Meeting [19th, transactions]

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

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

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

— 30 000 символов Nuclear power plant

— PWR Technology Cross Training Course

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

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