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REACTIVITY OF SUBSTITUTION ELEMENTS

Description: A method is sought for predicting reactivity differences between fuel elements attached to control absorbers and fixed fuel elements. The approach described is based on a logic that is approximate, and which should be subjected to experimental check. (auth)
Date: January 19, 1959
Creator: Murray, R.L.
Partner: UNT Libraries Government Documents Department
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Physics study of the TRADE : TRIGA accelerator driven experiment.

Description: This report deals with the validation of an ADS dynamic behavior through the TRADE program. We first describe the motivations behind the TRADE project. This includes the types of ADS experiments to be performed and their necessity, beam trips issues, representativity of the experiment, and steps to be taken in the validation procedure. Then we perform the characterization of the TRADE core using deterministic methods. The general core description is given. A number of results related to the core criticality and modeling with different geometries are presented. Finally we report the experimental results of the recent critical measurements including the control rod calibration, determination of the critical configurations and fluxes in the core.
Date: January 13, 2004
Creator: Naberejnev, D.; Imel, G.; Palmiotti, G. & Salvatores, M.
Partner: UNT Libraries Government Documents Department
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XENON TRANSIENT TESTS. CORE I, SEED 2. Section 1. Test Results T-612081

Description: A test was conducted to determine if sufficient excess reactivity exists in the core to override a peak xenon transient, and to obtain data for rod worth calculations. After completlon of 224.7 EFPH of plant operation with Core 1, seed 2 (5053.9 EFPH total Core I operation), there was sufficient reactivity to override the peak xenon transient imposed by a rapid station shutdown from an avernge reactor power level of 105.24%. Data on rod worth and other test results are included. (J.R.D.)
Date: January 30, 1961
Partner: UNT Libraries Government Documents Department
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Calculation of nuclear heating rates in LMFBR control rods

Description: The results of calculations of power densities and worths for control rods which use boron for neutron absorption are presented. The calculations were performed as a function of the control assembly core location, axial position, and /sup 10/B enrichment. (JWR)
Date: January 1, 1973
Creator: Gibson, G. & Dyos, M.W.
Partner: UNT Libraries Government Documents Department
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Control Rod Drive Development

Description: Equipment and procedures uscd in testing Army Package Power Reactor control rod drive mechanisms are described. Photographs of mechanism components taken before and after testing are included. (D.E.B.)
Date: August 15, 1957
Creator: Tully, J. P.; Connolly, T. F. & Anderson, R. E.
Partner: UNT Libraries Government Documents Department
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Hydraulic and Heat Transfer Transients During Power Ramp - Mark VII-AL Tests at Columbia University

Description: Transient tests were run at Columbia University on a Mark VII-AL mockup to reproduce the hydraulics and heat transfer in a single fuel assembly during a power ramp resulting from the accidental withdrawal of control rods from a reactor. This document presents results of those tests.
Date: January 6, 2003
Creator: Durant, W.S.
Partner: UNT Libraries Government Documents Department
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INSTRUMENT STANDARDS

Description: Hanford Atomic Production Operation specification guides for instruments, radiation detection instruments, instrumentation, thermocouples, orifices, process control instruments, and electronic design are presented. Details of this manual are given in TID-4100(Suppl.). (N.W.R.)
Date: January 1, 1963
Partner: UNT Libraries Government Documents Department
open access

The Marvel-Schebler Control Rod Drive System Design Review. Final Report

Description: The results and conclusions of a design review of the Marvel-Schebler control rod drive system are presented. The review included studies of mechanical design, electem reliability, system logic, component and logic failures, and system relationship to reactor safety. Work was not completed on the fault analysis, system packaging, and test recommendations. (auth)
Date: September 1, 1963
Partner: UNT Libraries Government Documents Department
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