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Functional Analysis and Thermal-Hydraulics Program Plan

Authors: Paik, I. K.; Lord, R.; Parks, B.;

Functional Analysis and Thermal-Hydraulics Program Plan

Abstract

The purpose of this document is to set forth the Program Plan for the Functional Analysis and Thermal-Hydraulics (FA TH) Program (herein after referred to as the [open quotes]Program[close quotes]) for the 5 year period covering fiscal years 1992 thru 1996. Specifically, the actions planned by the Safety Analysis Group (SAG) of the Reactor Safety Research Section within SRTC will be identified, defined, and a schedule and resource projection presented. This document will be used by the Reactor Safety Research Section management as the baseline definition for the Program's scope, schedule and cost. Annual budget and staffing requests will be submitted based on this approved baseline. Status reporting and progress monitoring will be performed against this approved baseline. This Program plan will be revised as needed to reflect the changes that come about due to Program redirection. The Program's primary mission is to provide further assurance that the Savannah River Site K-Reactor is designed, modified, operated and maintained in a safe, cost-effective manner through application of functional analysis methodology and continued development of thermal hydraulic support capabilities. It is envisioned that the Program will continue throughout the operating life of K-Reactor and have a permanent staff of eight: one leadmore » and seven engineers. The Program has two primary elements; (1) functional analysis, and (2) thermal-hydraulics. Functional analysis is the first element of the formal Systems Engineering Process. Systems Engineering methodology is commonly applied in both commercial and military programs, particularly where the needs of the program involve complex interrelationships between hardware, software, personnel, and support facilities. It has been extensively used in development of military systems, and in the commercial sector in the development of designs for nuclear power reactors.« less

Country
United States
Related Organizations
Keywords

Test, Monitoring, Cost, Production Reactors, Safety 220900* -- Nuclear Reactor Technology-- Reactor Safety, K Reactor, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 220600, Safety Analysis, Special Production Reactors 220900, Training, 220600 -- Nuclear Reactor Technology-- Research, Special Production Reactors, Reactor Safety, 22 General Studies Of Nuclear Reactors, Research, Production, Test & Experimental Reactors, Reactors, Management, Irradiation, Materials Testing Reactors, Heavy Water Moderated Reactors, Functional Analysis, Mathematics

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
0
Average
Average
Average