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Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1

Description: This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety a… more
Date: March 1976
Creator: Sackett, J. I. & Gale, N. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design-Development and Operation of the Experimental Boiling-Water Reactor (EBWR) Facility, 1955--1967

Description: The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(… more
Date: November 1990
Creator: Boing, L. E.; Wimunc, E. A. & Whittington, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Control Rods in LMFBRs: A Physics Assessment

Description: This physics assessment is based on roughly 300 control rod worth measurements in ZPPR from 1972 to 1981. All ZPPR assemblies simulated mixed-oxide LMFBRs, representing sizes of 350, 700, and 900 MWe. Control rod worth measurements included single rods, various combinations of rods, and tantalum and europium rods. Additional measurements studied variations in B4C enrichment, rod interaction effects, variations in rod geometry, neutron streaming in sodium-filled channels, and axial worth profile… more
Date: August 1982
Creator: McFarlane, Harold F. & Collins, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary, Analysis, and Comparison of Data from Experiments with the EBR-II Mark IIB Oscillator Rod

Description: The Mark IIB oscillator rod was used in EBR-II runs 48-55. Data were collected, digitized, and processed by on-line computer analysis, and Fourier analysis was used to obtain frequency-response functions. Feedback frequency-response functions are compared with those obtained by rod-drop experiments and are qualitatively identical. Experimental results are also compared with the EBR-II dynamic simulation computer program, EROS. Through the use of basic neutronic and heat-transfer principles, thi… more
Date: 1977?
Creator: Larson, H. A. & Dean, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-240Pu Sector Experiments in ZPPR Assembly 4

Description: The complete high-plutonium-240 fuel experiment in ZPPR assembly 4 is reviewed. Results of criticality, enrichment, small-sample perturbation, sodium void, uranium-238 Doppler, control rod substitution and reaction rate measurements are presented. Comparison of these measured values with calculated results are included where possible. The relationship between the ZPPR high-plutonium-240 fuel experiments and the results obtained in previous critical experience is considered.
Date: December 1976
Creator: McFarlane, Harold F. & Beck, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Formal System Specifications : a Case Study of Three Diverse Representations

Description: The only effective way to raise the confidence level of a program significantly is to give a convincing proof of its correctness. But one should not first make the program and then prove its correctness, because then the requirement of providing the proof would only increase the poor programmer's burden. On the contrary: the programmer should let correctness proof and program grow hand in hand.
Date: December 1990
Creator: Chisholm, G. H.; Smith, Brian Thomas & Wojcik, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of the Transient Correction Factor Used in TREAT Reactor In-Pile Experiments

Description: The transient correction factor (TCF) is used in TREAT reactor experiments to predict the power calibration coefficient (PC) for prototype LMFBR fuel pins at transient conditions without subjecting the pins to a reactor transient. The TCF is defined as the fissions in a monitor wire per MW of reactor power at transient conditions divided by the fissions in a monitor wire per MW of reactor power at low power conditions. The power calibration factor is the power in the target fuel gram of Uranium… more
Date: 1978?
Creator: Graff, Dale L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Approximate Models for Distributed-Parameter Heat-Transfer Systems

Description: Summary: The use of dimensionless-parameter frequency response diagrams to determine accuracies of lumped-parameter approximations is demonstrated by two examples: calculation of the heat flux at the surface of a semi-infinite solid due to temperature fluctuations of an adjacent fluid; and the response of a counterflow heat exchanger to inlet fluid temperature perturbations. Dimensionless system parameters make it possible to use general-purpose plots to find the error in particular approxima… more
Date: August 20, 1963
Creator: Ball, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Studies on Control of the Converter Reactor

Description: Introduction: "This report is an extension of NAA-SR-Memo-178. The results show the number of control rods as a function of the amount of reactivity to be controlled. Numerical solutions are given for a typical example and are readily obtainable for other cases."
Date: May 12, 1952
Creator: Robinson, L. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Operational Control Rod Reactivity Worths From Observed Heat Generation Rates

Description: Introduction. The reactivity difference associated with a reactor change can be simply related to the coincident changes in the neutron loss and generation rates. Unfortunately, in many instances these rates are difficult to measure directly during high-level operation; thus relativity values are normally found by other methods such as buckling calculations or low-level rising period measurements. However, with certain applicable control rod systems, it may be feasible to use heat generation… more
Date: October 1963
Creator: Fredsall, J. R. & Bowers, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Specifications and Fabrication Procedures on Europium-Bearing Absorber Rods for Reactivity Control in Core II of SM-1

Description: From abstract: "This report is concerned with the specifications and fabrication procedures developed and concerned with the specifications and fabrication procedures developed and adopted for manufacturing the prototype component."
Date: 195X
Creator: Leitten, C. F., Jr.; Beaver, R. J. & Cunningham, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of the Argonne Low Power Reactor (ALPR)

Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly… more
Date: May 1961
Creator: Hamer, Eberhard E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Argonaut Automatic Flux Controller Design Report

Description: Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.
Date: January 1960
Creator: Gerba, A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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