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B, D, F, DR, H reactor new aluminum HCR concept: Temperature study

Description: The horizontal control rods presently installed in the older Hanford Reactors have inadequate heat transfer characteristics for present and predicted future operation of the reactors. Continued graphite stack distortion, coupled with higher graphite temperatures, has resulted in ECR failure during reactor operation, such as swelling of the outer aluminum sheaths to the extent that rod movement in the graphite channel is severely restricted. Continued graphite stack distortion will tend to further aggravate the problem of rod operation. A new HCR design concept,was developed by P. H. Hutton of Reactor Design, IPD, to alleviate some of the pressing operational problems. Prior to the acceptance of such a design, the important rod operating parameters should be known to some degree of accuracy. This study was conducted to detexmine, by calculational methods, the temperature distributions that could be expected to occur in such an HCR when used at the present operating power levels and at 120% of the present power levels.
Date: July 28, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department

Top shield temperatures, C and K Reactors

Description: A modification program is now in progress at the C and K Reactors consisting of an extensive renovation of the graphite channels in the vertical safety rod ststems. The present VSR channels are being enlarged by a graphite coring operation and channel sleeves will be installed in the larger channels. One problem associated with the coring operation is the danger of damaging top thermal shield cooling tubes located close to the VSR channels to such an extent that these tubes will have to be removed from service. If such a condition should exist at one or a number of locations in the top shield of the reactors after reactor startup, the question remains -- what would the resulting temperatures be of the various components of the top shields? This study was initiated to determine temperature distributions in the top shield complex at the C and K Reactors for various top thermal shield coolant system conditions. Since the top thermal shield cooling system at C Reactor is different than those at the K Reactors, the study was conducted separately for the two different systems.
Date: December 28, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department

Authorization request for potential non-compliance with the American Standard Safety Code for Elevators Dumbwaiters and Escalators

Description: A Third Party inspection of the reactor work platforms was conducted by representatives of the Travelers Insurance Company in 1958. An inspection report submitted by these representatives described hazardous conditions noted and presented a series of recommendations to improve the operational safety of the systems. Project CGI-960, ``C`` & ``D`` Work Platform Safety Improvements -- All Reactors, vas initiated to modify the platforms in compliance with the Third Party recommendations. The American Standard Safety Code for Elevators Dumbwaiters and Escalators (A-17.1) is used as a guide by the Third Party in formulating their recommendations. This code is used because there is no other applicable code for this type of equipment. While the work platforms do not and in some cases can not comply with this code because of operational use, every effort is made to comply with the intent of the code.
Date: September 28, 1964
Creator: Boyd, J. E.
Partner: UNT Libraries Government Documents Department

Production Test IP-584-D, supplement B, irradiation of target assemblies in the KER Loops

Description: The objective of this supplement to Production Test IP-584-D is to authorize low exposure (5--8 GVR) irradiation tests of the following lithium-containing target materials: Magnesium -- 14 percent lithium alloy, Lithium-aluminate (LiA1O2), Lithium-silicate (Li2SiO), Lithium-aluminate -- aluminum cermet, Lithium-silicate -- aluminum cermet. Lithium target materials will be contained in 4.50 inch long aluminum cans which are clad with 35 mil Zircaloy-2 alloy. The target elements will be contained in 1.9 inch OD, 1.5 inch ID Zircaloy-2 flow distributing sleeves. The target element assemblies and N Reactor inner-fuel elements (NIE-1) in Zircaloy-2 sleeves, will be irradiated in KER-1 or KER-2 at operating conditions approximating N Reactor operation.
Date: April 28, 1964
Creator: Deobald, T. L.
Partner: UNT Libraries Government Documents Department

NBC Radio Broadcast: Toscanini - The Man Behind the Legend, 10/28/1964

Description: This recording is a part of the radio series “Toscanini: The Man Behind the Legend,” which was a tribute to conductor Arturo Toscanini. The broadcasts consist of music performed by the NBC Orchestra as well as interviews with composers, conductors, orchestra members, and other people associated with Toscanini. This segment includes performances of excerpts from Verdi's La forza del destino, Puccini's La traviata, La bohème, and an interview with Jan Pearce.
Date: October 28, 1964
Creator: Gillis, Don
Partner: UNT Music Library

ANALOG SOLUTION OF A MODEL OF THE SOURCES OF ELUTRIATABLE FINES IN THE FLUIDIZED BED CLACINATION PROCESS

Description: A model is proposed which depicts the sources of elutriatable fines in the fluidized bed calcination process as being in two major groups, spray drying mechanisms and attrition mechanisms. Based on this model, equations are derived which express the rate of change of the concentration of a chemical tracer material in the elutriated fines, following introduction of the tracer into the feed and following its removal from the feed. This system has been simulated on an analog computer, and by matching the computer simulation to results from an actual calciner run, the rates of generation of fines by each of the two groups of mechanisms has been determined; the same technique results in an estimate of the amount of these fines remaining in the fluidized bed. Agreement between postulated results and results of actual experimental tests lends credence to the usefulness of this analytical technique. (auth)
Date: February 28, 1964
Creator: Grimmett, E.S.
Partner: UNT Libraries Government Documents Department

Technical note on the determination of K-reactor last-ditch cooling adequacy

Description: The Hanford reactors contain a very large inventory of fission products and it is very important that this inventory be contained. In recognition of this, rather stringent reactor cooling requirements have been established for the Hanford reactors. This includes the requirement of three independent cooling systems, including the system for full level operation. The second and last-ditch systems both are usable only after a reactor scram and take-over automatically from the flywheel decay of the process pumps. In 1962, two projects were completed that affected the last-ditch cooling adequacy of the K reactors, One project increased the reactor pumping capacity and, therefore, its power level; and the other considerably modified the emergency cooling systems. Since this time, three tests have been conducted to determine this last-ditch cooing adequacy. In order to provide a uniform approach to this adequacy determination, the method employed by Reactor Engineering is presented herein. The report presents a method for determining the maximum reactor power level for which measured last-ditch flows will provide adequate emergency cooling, A number of pertinent charts are included, A method is also presented for determining the last-ditch flow that should be measured during a test for any desired level of normal reactor operation.
Date: February 28, 1964
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department

Report of invention: Increasing amounts of Pu-241 isotope

Description: This invention report suggests a method for drastically increasing the amount of Pu-241 in isotopic mixtures of plutonium. It is felt that with process experience, as much as 70 percent or more of the potential Pu-241 atoms can be concentrated in the fuel at one time. Such a concentration step would double the amount of production obtainable from Pu-241 by nuclear decay. The process to concentrate the Pu-241 consists of two basic steps: 1. Irradiate plutonium consisting largely of Pu-239 isotope until the Pu-239 has largely been converted to Pu-240 and 241 by thermal neutron fission and absorption events. Most of the fuel value has been taken advantage of at this point. The isotopic mixture will be largely Pu-240 but contain smaller percentages of 241 and 239. The irradiation is terminated at this point and the products are separated. 2. The depleted plutonium isotopes from the first irradiation are refabricated for a second irradiation with a thermal neutron absorber surrounding the depleted plutonium isotope. This element is again irradiated, preferably in an epithermal neutron flux with a peak energy slightly above 1 ev. The Pu-240 has a huge resonant cross section at the 1 ev level and will be most rapidly converted to Pu-241 by neutrons of this energy. The Pu-241 has a minimum reactor cross section for neutrons of 1 ev and thus will not be destroyed faster than created if the atoms are protected from the thermal neutrons by a cutoff absorber.
Date: January 28, 1964
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department