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Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1994-06)
A design for a large, passive, light water reactor has been developed. The proposed concept is a pressure tube reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid SiC-coated ...
Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1994-06-01)
A design for a large, passive, light water reactor has been developed.
The proposed concept is a pressure tube reactor of similar design to
CANDU reactors, but differing in three key aspects. First, a solid
Sic-coated ...
Use of Performance Monitoring to Improve Reliability of Emergency Generators Diesel
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1997-12)
Emergency diesel generators are one of the most important contributors to the core damage failure rate of nuclear power plants. Current required testing and maintenance procedures are excessively strict and expensive without ...
Risk-Informed, Performance-Based Regulatory Implications of Improved Emergency Diesel Generator Reliability
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1998-01)
The Nuclear Regulatory Commission's (NRC) steady progress towards risk-informed
performance-based regulation (RIPBR) prompted the practical application of this
regulatory tool in order to demonstrate its potential benefits. ...
A Semi-Passive Containment Cooling System Conceptual Design
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1998-02)
The objective of this project was to investigate a passive containment cooling system (PCCS) for the double concrete containment of the Korean Next Generation Reactor (KNGR). Two conceptual PCCS designs: the thermosyphon ...
An Integrated Formal Approach for Developing High Quality Software for Safety-Critical Systems
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1995-09)
This report presents the results of a study which devises an Integrated Formal Approach (IFA) for improving specifications of the designs of computer programs used in safety-critical systems. In this IFA, the formal ...