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Title: Special power supply and control system for the gas-cooled fast reactor-core flow test loop

Abstract

The test bundle in the Gas-Cooled Fast Reactor-Core Flow Test Loop (GCFR-CFTL) requires a source of electrical power that can be controlled accurately and reliably over a wide range of steady-state and transient power levels and skewed power distributions to simulate GCFR operating conditions. Both ac and dc power systems were studied, and only those employing silicon-controlled rectifiers (SCRs) could meet the requirements. This report summarizes the studies, tests, evaluations, and development work leading to the selection. it also presents the design, procurement, testing, and evaluation of the first 500-kVa LMPL supply. The results show that the LMPL can control 60-Hz sine wave power from 200 W to 500 kVA.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
6170559
Report Number(s):
ORNL/TM-7845
ON: DE81030435; TRN: 81-016003
DOE Contract Number:
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; GCFR REACTOR; MOCKUP; POWER SUPPLIES; PERFORMANCE; SPECIFICATIONS; TEST FACILITIES; ORNL; BREEDER REACTORS; ELECTRONIC EQUIPMENT; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GCFR TYPE REACTORS; HELIUM COOLED REACTORS; NATIONAL ORGANIZATIONS; REACTORS; STRUCTURAL MODELS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; 210500* - Power Reactors, Breeding

Citation Formats

Hudson, T.L. Special power supply and control system for the gas-cooled fast reactor-core flow test loop. United States: N. p., 1981. Web. doi:10.2172/6170559.
Hudson, T.L. Special power supply and control system for the gas-cooled fast reactor-core flow test loop. United States. doi:10.2172/6170559.
Hudson, T.L. 1981. "Special power supply and control system for the gas-cooled fast reactor-core flow test loop". United States. doi:10.2172/6170559. https://www.osti.gov/servlets/purl/6170559.
@article{osti_6170559,
title = {Special power supply and control system for the gas-cooled fast reactor-core flow test loop},
author = {Hudson, T.L.},
abstractNote = {The test bundle in the Gas-Cooled Fast Reactor-Core Flow Test Loop (GCFR-CFTL) requires a source of electrical power that can be controlled accurately and reliably over a wide range of steady-state and transient power levels and skewed power distributions to simulate GCFR operating conditions. Both ac and dc power systems were studied, and only those employing silicon-controlled rectifiers (SCRs) could meet the requirements. This report summarizes the studies, tests, evaluations, and development work leading to the selection. it also presents the design, procurement, testing, and evaluation of the first 500-kVa LMPL supply. The results show that the LMPL can control 60-Hz sine wave power from 200 W to 500 kVA.},
doi = {10.2172/6170559},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1981,
month = 9
}

Technical Report:

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  • The Core Flow Test Loop was constructed to perform many of the safety, core design, and mechanical interaction tests in support of the Gas-Cooled Fast Reactor (GCFR) using electrically heated fuel rod simulators (FRSs). Operation includes many off-normal or postulated accident sequences including transient, high-power, and high-temperature operation. The FRS was developed to survive: (1) hundreds of hours of operation at 200 W/cm/sup 2/, 1000/sup 0/C cladding temperature, and (2) 40 h at 40 W/cm/sup 2/, 1200/sup 0/C cladding temperature. Six 0.5-mm type K sheathed thermocouples were placed inside the FRS cladding to measure steady-state and transient temperatures through cladmore » melting at 1370/sup 0/C.« less
  • The core flow test loop, which is part of the Gas-Cooled Fast Breeder Reactor Program (GCFR) at ORNL, is a high-pressure, high-temperature, out-of-reactor helium circulation system that is being constructed to permit study of the performance at steady-state and transient conditions of simulated segments of core assemblies for a GCFR demonstration plant. The simulated core segments, which are divided into zones, contain electrical heating elements to simulate the heat generated by fission. To control the power which is applied to a zone, a novel multitapped transformer and zone power control system have been designed and built which satisfy stringent designmore » criteria. The controller can match power output to demand to within better than +-1% over a 900:1 dynamic range and perform full-power transients within 1 s. The power is applied in such a way as to minimize the electromagnetic interference at the bandwidth of the loop instrumentation, and the controller incorporates several error detection techniques, making it inherently fail-safe. The operation manual describes the specifications, operating instructions, error detection capabilities, error recovery, troubleshooting, calibration and QA procedures, and maintenance requirements. Also included are sections on the theory of operation, circuitry description, and a complete set of schematics.« less
  • This work represents a status report on a development effort to design an ac power controller for the Core Flow Test Loop. The Core Flow Test Loop will be an engineering test facility which will simulate the thermal environment of a gas-cooled fast-breeder reactor. The problems and limitations of using sinusoidal ac power to simulate the power generated within a nuclear reactor are addressed. The transformer-thyristor configuration chosen for the Core Flow Test Loop power supply is presented. The initial considerations, design, and analysis of a closed-loop controller prototype are detailed. The design is then analyzed for improved performance possibilitiesmore » and failure modes are investigated at length. A summary of the work completed to date and a proposed outline for continued development completes the report.« less
  • A digital simulation program, ORCULT-I, was developed to predict both the steady-state and transient behavior of the core flow test loop (CFTL). ORCULT has been used to answer design questions concerning loop configurations, operating modes, bundle tests, and postulated loop-accident conditions. The CFTL is a thermal-hydraulic and structural test vehicle for performance evaluations of Gas-Cooled Fast-Breeder Reactor (GCFR) fuel-rod bundle designs. The status, capabilities, and limitations of ORCULT are described, and several sample transients are shown which demonstrate characteristics of CFTL behavior. The appendix of the report includes derivations of the model equations used in ORCULT.