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Bibliography on General Test Reactors

Description: Bibliographies on the MTR ETR, G. E. Materials Testing Reactor, Vallecitos Boiling Water Reactor, and Westinghouse Testing Reactor are presented. In addition, bibliographies of miscellaneous reactors and inpile loops are included. Sources used are Engineering Index, 1951 to 1958, Industrial Arts Indes. 1951 to July 1959, and Nuclear Science Abstracts, 1948 to August 15, 1959. (J.R.D.)
Date: September 1, 1959
Creator: Duke, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Engineering Test Reactor

Description: A relatively inexpensive reactor for the specific purpose of testing a sub-critical portion of another reactor under conditions that would exist during actual operation is discussed. It is concluded that an engineering tool for reactor development work that bridges the present gap between exponential and criticality experiments and the actual full scale operating reactor is feasible. An example of such a test reactor which would not entail development effort to ut into operation is depicted.
Date: March 16, 1951
Creator: Fahrner, T.; Stoker, R.L. & Thomson, A.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Burn-up Tests on U-Al Fuel Elements

Description: The desired neutron spectrum for the High Flux Beam Reactor under construction at BNL requires use of U-Al fuel elements with more then 30 wt% U235 in the meat. The operating cycle of this reactor requires a minimum burn-up of 20%, and preferably 40% of the uranium in the element.
Date: March 3, 1964
Creator: Weeks, J. R.; McRickard, S. B. & Gurinsky, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Etr Gamma Heat Generation Measurements for Cycles 27, 33, and 34

Description: The gamma heat generations in selected positions of the ETR were measured for Cycles 27, 33, and 34. The measurements for Cycle 27 include data for the clean core and depleted core. Maximum gamma heat generation maps are presented for each cycle along with vertical traverses for all positions monitored. The measurements were made using a graphite- C0/sub 2/ ionization chamber. (auth)
Date: May 31, 1961
Creator: Weber, L. D. & Hogg, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Action Memorandum for the Engineering Test Reactor under the Idaho Cleanup Project

Description: This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared and released for public comment. The scope of this Action Memorandum is to encompass the… more
Date: January 26, 2007
Creator: Culp, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Etr Flux Measurements for Cycles 51b and 54

Description: The thermal-neutron fluxes in the lattice positions and selected experimental positions of the ETR were measured for Cycle 51B. Gamma heat generation was also measured in various experimental positions for Cycles 51B and 54. Vertical traverses for each position monitored are shown. (auth)
Date: July 15, 1963
Creator: Weber, L. D. & Hogg, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of an Advanced Engineering Test Reactor Design

Description: The scope of the study was primarily concerned with optimization of the geometrical and core-composition variables to achieve maximum flux in the loop region per unit core power without exceeding heat transfer and other engineering limitations. Centain other design questions are to be investigated. (A.C.)
Date: July 15, 1958
Creator: McVey, Marvin; Bradfute, J. O.; Buck, K. E.; Chow, K. T.; Jaffee, R. J.; Quilici, R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Element Flow Blockage in the Engineering Test Reactor

Description: On December 12, 196l, the Engineering Test Reactor experienced fuel fission breaks which resulted from obstructions to the flow of cooling water through several fuel elements. A total of six fuel elements had breaks in from one to eight fuel plates. A discussion and description of damage to the fuel is presented. The reactor operating conditions preceding the break are described, including events immediately before the manual scram. Results of investigations conducted after the scram, including… more
Date: May 10, 1962
Creator: Keller, F. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CARBIDE FUEL DEVELOPMENT. Progress Report, April 1, 1962 to June 30, 1962

Description: All of the UC-PuC powder required for the natural U irradiation specimens, and some of the powder required for the enriched U irradiation specimens was synthesized. All of the natural uranium UC-PuC pellets required were fabrlcated by pressing and sintering, and are being ground to size. The average density of the (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ pellets was 12.54 g/cm/ sup 3/ (92.4% of theoretical) and of the (U/sub 0.08/Pu/sub 0.2/)C/sub 0.95/ plus 0.1 wt% Ni pellets was 13.15 g/cm/sup 3 (9… more
Date: August 10, 1962
Creator: Strasser, A. & Taylor, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

Description: The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pend… more
Date: October 1, 1994
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-237-A, irradiation of enriched seven-rod cluster elements for ETR testing

Description: Two Zircaloy-2 jacketed seven-rod cluster elements will be irradiated in the 3674 KE front-to-rear test hole to an exposure of 1000 MWD/T and two elements will be irradiated in the 3674 KW front-to-rear test hole to an exposure of 2000 MWD/T. After irradiation, the elements will be sent to the ETR where they will be ruptured during reactor operation to determine the failure characteristics of co-extruded Zircaloy-2 jacketed cluster elements.
Date: February 23, 1959
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in len… more
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimation of Critical Flow Velocity for Collapse of Gas Test Loop Booster Fuel Assembly

Description: This paper presents calculations performed to determine the critical flow velocity for plate collapse due to static instability for the Gas Test Loop booster fuel assembly. Long, slender plates arranged in a parallel configuration can experience static divergence and collapse at sufficiently high coolant flow rates. Such collapse was exhibited by the Oak Ridge High Flux Reactor in the 1940s and the Engineering Test Reactor at the Idaho National Laboratory in the 1950s. Theoretical formulas outl… more
Date: July 1, 2006
Creator: Guillen & Russell, Mark J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Engineering Capabilities of in-Pile Irradiation Facilities Used by GE-ANPD

Description: GE-ANPD had exclusive use of irradiation testing facilities in four reactors: the Materials Test Reactor (MTR), the Engineering Test Reactor (ETR), the Low lntensity Test Reactor (LlTR), and the Oak Ridge Research Reactor (ORR). A compilation of data concerning the GE-ANPD facilities in these reactors is presented. lnstrumentation capabilities, dimensions of the in-pile tubes, flow characteristics, control capabilities, and detailed design data are listed. (auth)
Date: October 1, 1961
Creator: Harry, R. J. & Fries, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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