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Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants

given to the basic set of attributes characterizing a `base case PSA' that is performed to assess overall plant safety. The present publication;

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Consideration of External Hazards in Probabilistic Safety Assessment for Single Unit and Multi-Unit Nuclear Power Plants.

Outlines the generic methodology for probabilistic safety assessment (PSA) of nuclear power plants (NPPs) against external hazards. This;

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Safety Aspects of Nuclear Power Plants in Human Induced External Events

probability and the conditional probability of spent fuel damage. In the most elaborated stage, probabilistic safety assessment (PSA) techniques are;

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Probabilistic Safety Assessment for Optimum Nuclear Power Plant Life Management (PLiM)

, Probabilistic safety assessment for optimum nuclear power plant life management is a valuable reference for all nuclear plant designers, operators;

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Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants

Series No. SSR-2/2 (Rev.1), Safety of Nuclear Power Plants: Commissioning and Operation. It provides guidance for operating organizations on;

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Risk Importance Measures in the Design and Operation of Nuclear Power Plants

In using risk-informed approaches for ensuring safety of operating nuclear power plants (NPPs), risk importance measures obtained from;

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Safety of Nuclear Power Plants: Commissioning and Operation

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended;

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Safety of Nuclear Power Plants: Commissioning and Operation

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended;

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Safety of Nuclear Power Plants: Commissioning and Operation

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended;

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Safety of Nuclear Power Plants: Commissioning and Operation

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended;

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Risk and Safety Analysis of Nuclear Systems

, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical;

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Design of Electrical Power Systems for Nuclear Power Plants

This Safety Guide provides recommendations on the necessary characteristics of electrical power systems for nuclear power plants, and;

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Lessons Learned from the Fukushima Nuclear Accident for Improving Safety of U.S. Nuclear Plants

eventual shutdown of all nuclear power plants in Japan. Lessons Learned from the Fukushima Nuclear Accident for Improving Safety and Security;

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Safety Aspects of Nuclear Power Plants in Human Induced External Events: Assessment of Structures

Provides detailed guidelines for the safety assessment of nuclear power structures against mechanical impact, explosion and fire caused by;

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Nuclear Power

. Table of Contents Front Matter Summary 1 Introduction 2 The Institutional Framework 3 Assessment of Advanced Nuclear Reactor;

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Criteria for Diverse Actuation Systems for Nuclear Power Plants

This publication addresses a safety concern within the protection system for nuclear power plants that might result in unacceptable;

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Format and Content of the Safety Analysis Report for Nuclear Power Plants

Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi;

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Design of the Reactor Containment and Associated Systems for Nuclear Power Plants

gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for;

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Safety Aspects of Nuclear Power Plants in Human Induced External Events

the important considerations for its application to existing and new nuclear power plants. Topics covered include elements of the design;

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Dependability Assessment of Software for Safety Instrumentation and Control Systems at Nuclear Power Plants

control software used at nuclear power plants. It describes an approach for developing and communicating assessments based on claims, argument and;

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Safety of Nuclear Power Plants

concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant.;

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants;

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Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants

) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G;

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Reliability and Safety Engineering

power systems engineering. The book describes the latest applications in the area of probabilistic safety assessment, such as technical;

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Safety Design Criteria for Industrial Plants

safety analyses are described, together with the methodologies for seismic analyses and for Probabilistic Risk Assessment. The main criteria for;

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Safety Design Criteria for Industrial Plants

safety analyses are described, together with the methodologies for seismic analyses and for Probabilistic Risk Assessment. The main criteria for;

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Nuclear Power Plants

modeling of critical parameters in nuclear power plants, thermal-hydraulic analysis, nuclear waste management and safety assessment. The book;

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