Open AccessPATHFINDER ATOMIC POWER PLANT. IBM-704 PROGRAM FOR REACTOR CONTAINMENT, PRESSURE SUPPRESSION ANALYSIS
Author(s) -
E.E. Mason,
W.M. Chmielewski
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4120201
Subject(s) - nuclear engineering , boiler feedwater , containment (computer programming) , coolant , environmental science , reactor pressure vessel , triga , computer program , research reactor , computer science , engineering , nuclear physics , mechanical engineering , neutron , waste management , boiler (water heating) , physics , operating system , programming language
A research and development program to investigate the feasibility of eliminating vapor closure for the Pathfinder Reactor was conducted. The major inquiry under the feasibility study involved an analysis of the complex transient conditions occurring in the reactor cavity, the pump rooms, and the entire reactor building following a primary system rupture. To solve the simultaneous nonlinear set of equations evolving from the heat, mass, and force balances in the system, an IBM-704 digital computer program was developed. The program has a very general input and can therefore be used with other containment designs. Input parameters include: initial pressures in reactor and throughout the containment building, hent capacity of vessel, decay heat, feedwater flow rate, enthalpy of feedwater, and volume of primary coolant system. (auth
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