Showing papers on "Inherent safety published in 1991"
TL;DR: In this article, the authors demonstrate inherent safety characteristics incorporated into small high-temperature gas-cooled nuclear power plants to demonstrate the inherent safety properties of small high temperature gas cooled plants.
Abstract: A loss-of-coolant accident (LOCA) is one of the most severe accidents for a nuclear power plant. To demonstrate inherent safety characteristics incorporated into small high-temperature gas-cooled r...
23 citations
Journal Article•
14 citations
TL;DR: In this paper, it is shown that if there were a large program of inherently safe reactors, the safety objectives would be determined more by investment risk than by the public health risk, which leads to an objective on the order of 1 × 10 −7 per r.yr (reactor year) for the probabability of a severe core damage accident.
8 citations
01 Sep 1991
TL;DR: The concept of passive safety, resilience, inherent safety, malevolence resistance, and extended time after initiation of an accident for external help was introduced in the early 1970s as discussed by the authors.
Abstract: The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: whymore » a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.« less
5 citations
29 Jan 1991
TL;DR: The application of a cause-consequence analysis technique is reviewed in order to summarize the safety concerns and proposed safeguards for a generic space station computer system.
Abstract: The application of a cause-consequence analysis technique is reviewed in order to summarize the safety concerns and proposed safeguards for a generic space station computer system. The cause-consequence diagram presents a summary of causal factors for the initiating event. The diagram also identifies the inherent safety features of the computer system (both hardware and software) that preclude unwanted command and control functions. Additional safeguards needed to prevent or minimize the occurrence of safety critical hazards are shown in the event tree portion of the diagram. A complex safety analysis of a computer system application is summarized for management review. >
3 citations
TL;DR: In this article, a relative measurement system that uses reaction time factors to produce quantitative values that can be used to define when the term "inherent" is valid, when "passive" is more appropriate, and when neither one should be used.