UID:
almahu_9948025336102882
Umfang:
1 online resource (447 p.)
Ausgabe:
1st ed.
ISBN:
1-280-64229-7
,
9786610642298
,
0-08-046078-X
Inhalt:
Nuclear Safety is a comprehensive reference for heath & safety and engineering professionals in the nuclear industry and related bodies, including regulatory authorities, environmental and energy scientists, students, researchers and consultants. It provides the methods and data needed to evaluate and manage the safety of nuclear facilities and related processes using risk-based safety analysis, and provides readers with the techniques to assess the consequences of radioactive releases. The book covers relevant international and regional safety criteria (US, IAEA,
Anmerkung:
Description based upon print version of record.
,
Front cover; Title page; Copyright; Table of contents; Preface; Acknowledgements; Chapter 1 Introduction; 1-1. Objectives; 1-2. A short history of nuclear safety technology; 1-2-1. The early years; 1-2-2. From the late 1950's to the Three Mile Island accident; 1-2-3. From the Three Mile Island accident to the Chernobyl accident; 1-2-4. The Chernobyl accident and after; References; Chapter notes; Chapter 2 Inventory and localization of radioactive products in the plant; References; Chapter 3 Safety systems and their functions; 3-1. Plant systems; 3-2. Safety systems and accidents
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3-3. Future safety systems and plant concepts 3-3-1. General remarks; 3-3-2. Some passive safety systems for nuclear plants; 3-3-3. Inherently safe systems in the process industries; References; Chapter notes; Chapter 4 The classification of accidents and a discussion of some examples; 4-1. Classification; 4-2. Design basis accidents; 4-2-1. Some important data for accident analysis; 4-2-2. Example of a category 2 accident: spurious opening of a pressurizer safety valve; 4-2-3. Example of a category 3 accident: instantaneous power loss to all the primary pumps
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4-2-4. Example of a category 4 accident: main steam line break 4-2-5. Example of a category 4 accident: sudden expulsion of a control rod from the core; 4-2-6. Example of a category 4 accident: break of the largest pipe of the primary system (large LOCA); 4-2-7. Example of a category 4 accident: fuel handling accident; 4-2-8. Area accidents; 4-3. Beyond design basis accidents; 4-3-1. Plant originated accidents; 4-3-2. Accidents due to human voluntary actions; 4-4. External accidents of natural origin; References; Chapter notes; Chapter 5 Severe accidents; 5-1. Existing plants
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5-2. Future plants: extreme and practicable solutions 5-3. Severe accident management: the present state of studies and implementations; 5-4. Data on severe accidents; 5-5. Descriptions of some typical accident sequences; 5-5-1. Loss of station electric power supply (TE = transient + loss of electrical supply); 5-5-2. Loss of electric power with LOCA from the pump seals (SE = small LOCA + loss of electric power); 5-5-3. Interfacing systems LOCA (V); 5-5-4. Large LOCA with failure of the recirculation (ALFC); 5-5-5. Small LOCA with failure of the recirculation (SLFC)
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5-6. 'Source terms' for severe accidents References; Chapter 6 The dispersion of radioactivity releases; 6-1. The most interesting releases for safety evaluations; 6-2. Dispersion of releases: phenomena; 6-3. Release dispersion: simple evaluation techniques; 6-4. Formulae and diagrams for the evaluation of atmospheric dispersion; Reference; Chapter notes; Chapter 7 Health consequences of releases; 7-1. The principles of health protection and safety; 7-2. Some quantities, terms and units of measure of health physics; 7-3. Types of effects of radiation doses and limits
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7-4. Evaluation of the health consequences of releases
,
English
Weitere Ausg.:
ISBN 0-7506-6723-0
Sprache:
Englisch
