Evaluation of fire models for nuclear power plant applications

cable tray fires : international panel report

Publisher: U.S. Dept. of Commerce, Technology Administration, National Institute of Standards and Technology in Gaithersburg, MD

Written in English
Published: Downloads: 767
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  • Nuclear power plants -- Fires and fire prevention -- Research,
  • Nuclear power plants -- Fires and fire prevention -- Mathematical models,
  • Nuclear reactors -- Fires and fire prevention -- Research,
  • Nuclear reactors -- Fires and fire prevention -- Mathematical models,
  • Fire prevention -- Research

Edition Notes

Other titlesCable tray fires
Statementcompiled by Monideep K. Dey
SeriesNISTIR -- 6872
ContributionsDey, Monideep K, Building and Fire Research Laboratory (U.S.), National Institute of Standards and Technology (U.S.)
The Physical Object
Pagination1 v. (various pagings)
ID Numbers
Open LibraryOL15441415M

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Title Evaluation of fire models for nuclear power plant applications, cable tray fires [electronic resource]: international panel report / compiled by Monideep K.

Dey, Fire Research Division, Building and Fire Research Laboratory. Evaluation of fire models for nuclear power plant applications cable tray fires: international panel report.

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[Monideep K Dey; U.S. Nuclear Regulatory Commission. Division of Risk Analysis and Applications.]. Get this from a library.

Evaluation of fire models for nuclear power plant applications, cable tray fires: international panel report. [Monideep K Dey; Building and Fire Research Laboratory (U.S.); National Institute of Standards and Technology (U.S.);].

This document presents a shortened version of the procedure, models, and data for human reliability analysis (HRA) which are presented in the Handbook of Human Reliability Analysis With emphasis on Nuclear Power Plant Applications (NUREG/CR, August ).

The purpose of this study is to introduce a new and efficient virtual model-based ergonomic simulation framework utilizing recent anthropometric data for a digitalized main control room in an advanced nuclear power plant.

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@article{osti_, title = {Tornado missile risk analysis: probability modeling, simulation methodology, and case studies.

Final report. [TORMIS code]}, author = {Twisdale, L.A. and Dunn, W.L. and Chu, J.}, abstractNote = {Mathematical models of the contributing events to the tornado missile hazard at nuclear power plants have been developed in which the major sources of uncertainty have. While there are many resources available on fire protection and prevention in chemical petrochemical and petroleum plants—this is the first book that pulls them all together in one comprehensive resource.

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Statistical Characterization of Cable Electrical Failure Temperatures Due to Fire for Nuclear Power Plant Risk Applications. Nuclear Consultants International, LLC (NCI) is an autonomously constituted business unit of Holtec International.

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In this paper, auto-regressive integrated moving average (ARIMA) time-series data forecast models are evaluated to ascertain their feasibility in predicting human–machine interface (HMI) state transitions, which are modeled as multivariate time-series patterns. Human–machine interface states generally include changes in their visually displayed information brought about due to both process Author: Harsh V.

Singh, Qusay H. Mahmoud. Comparison of Radiation Embrittlement Prediction Models to High Fluence U.S. Power Reactor Surveillance Data. Brian Hall, William Server, Long Term Operation of Nuclear Power Plants: Status in the U.S. Garry G. Young. Practical Thermal Evaluation Methods for HAC Fire Analysis in Type B Radioactive Material (RAM) Packages.

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monitor and, when necessary, override the machine applications to ensure safe operation. A safety-related system thus implements the required safety functions by detecting hazardous conditions and bringing operation to a safe state, by ensuring that a desired action, e.g.

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