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Analog computer serves as both systems analysis tool and operator training facility for Enrico Fermi Atomic Power Plant

Authors:

Samuel N. Irwin,

Robert R. KleyAuthors Info & Claims

IRE-AIEE-ACM '60 (Western): Papers presented at the May 3-5, 1960, western joint IRE-AIEE-ACM computer conference

Pages 301 - 313

https://doi.org/10.1145/1460361.1460402

Published: 03 May 1960 Publication History

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Abstract

An analog simulator with specially designed electromechanical equipment was developed to simulate one of three loops of the Enrico Fermi Atomic Power Plant, including all elements except the steam turbine; i.e., the reactor, intermediate heat exchanger, steam generator, mixing and transport delay phenomena, and steam system hydraulics.

A philosophy of plant control was evolved on the basis of plant operating characteristics, as determined by the simulator and supported by a steady-state digital analysis of the plant. Conceptual control hardware designs were then tested on the simulator and an optimum design was selected and tuned. Actual hardware of the automatic control system was simulated, and this simulation circuitry incorporated in the computer.

Control consoles exactly duplicating the control panel layout in the actual plant were connected to the analog simulator to adapt it for power plant operator training. Trainees thus get the "feel" of plant operating characteristics, learn to meet emergencies, and practice standard operating procedures, using both manual and automatic controls.

The facility has already proved valuable in studying normal and abnormal operating conditions and remains available for any future systems analysis needs; meanwhile it is in continuing service for operator training.

References

[1]

Vernon Larrowe, "Direct Simulation Bypasses Mathematics," Control Engineering, Nov. 1954, pp. 25--31.

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[2]

"Design of the Reactor Normal Operating Control System for the Enrico Fermi Power Plant with Analog Computer Verification," Research Report No. 1191, Project J. O. 1960BC, Apr. 15, 1959, with addendum of June 23, 1959, Bailey Meter Co., Cleveland, Ohio.

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[3]

J. P. Franz and N. F. Simcic, "Nuclear Reactor Start-Up Simulation," I.R.E. Transactions on Nuclear Science, Mar. 1957, pp. 11--14.

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IRE-AIEE-ACM '60 (Western): Papers presented at the May 3-5, 1960, western joint IRE-AIEE-ACM computer conference

May 1960

391 pages

ISBN:9781450378697

DOI:10.1145/1460361

Conference Chair:
R. M. Bennett
IBM Corp., San Jose, California

Permission to make digital or hard copies of all or part of this work for personal or classroom use is granted without fee provided that copies are not made or distributed for profit or commercial advantage and that copies bear this notice and the full citation on the first page. Copyrights for components of this work owned by others than ACM must be honored. Abstracting with credit is permitted. To copy otherwise, or republish, to post on servers or to redistribute to lists, requires prior specific permission and/or a fee. Request permissions from [email protected]

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Association for Computing Machinery

New York, NY, United States

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Published: 03 May 1960

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Computer aided modeling and analysis of five-phase PMBLDC motor drive for low power high torque application

Dynamic analysis of the boiler drum of a coal-fired thermal power plant

Energy and Exergy Analysis for 300MW Thermal System of Xiaolongtan Power Plant

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