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FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954

Description: Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up … more
Date: December 1, 1954
Creator: Siegel, S. & Inman, G.M. eds.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Removal of cesium from uranium recovery process wastes

Description: The Uranium Recovery Process (TBP Process) at Hanford extracts and decontaminates uranium from the Metal Waste produced in the Bismuth Phosphate Process. Aqueous waste, approximately equal in volume to that of the Metal Waste itself, results from the process. Although of several years' age, these wastes are still sufficiently radioactive that they must be returned to underground tanks for storage. For several years aqueous wastes of low radioactive content have been discharged to ground at Hanf… more
Date: May 17, 1954
Creator: Burns, R. E.; Brandt, R. L. & Clifford, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ruthenium process chemistry considerations: Redox process

Description: During the first 15 months of operation of the Redox process, it was clearly demonstrated that in the absence of any pre-solvent extraction treatment of the starting metal solution, ruthenium contributed from 75 to 95% of the remaining fission product activity in both the final uranium and plutonium streams, and that three solvent extraction cycles were able consistently to produce, at best, only marginal quality product. This precarious position was further endangered by a three-fold reduction… more
Date: June 10, 1954
Creator: Harmon, M. K.; McCormack, C. G.; Moore, R. L. & Wilson, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nitric acid recovery and ammonia removal: Modifications to the Redox dissolver off-gas systems

Description: Project CG-588 authorized the design and construction of dissolver and waste neutralizer off-gas scrubbers to remove the ammonia given off during coating removal and waste neutralization steps of the Redox operation. It has always been recognized that the nitrogen oxides in the dissolver off-gases, resulting from the dissolution of bare uranium slugs, could also be absorbed in water under proper conditions to give re-useable nitric acid. Consequently it appeared feasible to provide facilities w… more
Date: October 1, 1954
Creator: Stoker, D. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sampling SX-tank farm condensate

Description: In accordance with the policy that a centralized inventory shall be kept of all radioactive waste liquid discharged to ground, it is recommended that the volumes of condensate from the SX-farm, the dates or periods of discharge, and the activity densities of radioisotopes in the condensate discharged be determined by Separations Section and reported regularly to the Radiological Standards Unit. This paper is a description of the condensate system, with recommendations for sampling and analysis.
Date: May 7, 1954
Creator: Clukey, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Disposal of irradiated waste Ink'' solution (Production Test 105-529-A)

Description: Boron solution circulated through special poison tubes to achieve more variable control of neutron flattening'' was tested in the 100-DR Hanford reactor. About 2700 gallons of irradiated waste Ink solution from Production Test 105-529-A was discharged to an underground crib at 100-DR, after radiochemical analyses and evaluation of radiation protection aspects by the Radiological Sciences Department. In case the Ink method is considered for production use at Hanford in the future, further biolog… more
Date: July 20, 1954
Creator: Clukey, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Slug and tube factors

Description: A common and useful assumption is that the front-to-rear power distribution is a shortened cosine curve. This fact led to the calculation of slug factors'' for the longer charges to be used at K-Pile. It is hoped that the publication of these numbers will save time and prevent duplication of effort by those concerned in any way with slug power, surface temperatures, reactivity effects, etc. For the sake of completeness, slug factors for the older piles are included. Another useful ideal is that… more
Date: May 13, 1954
Creator: Moon, M.R. & Brugge, R.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design considerations regarding slug ruptures in the intermediate power level reactor

Description: The minimum shutdown time, to permit accessibility, for the Intermediate Power Reactor is estimated to be 38 hours. In case the reactor were shutdown following each rupture this long shutdown period would have serious disadvantages. The desirability of being able to make firm power commitments (independent of slug ruptures) has led to a study of the possibility of continuous operation following a rupture. There is evidence to indicate that, at the proposed water temperature, the rate of corrosi… more
Date: November 1, 1954
Creator: Pearl, W. L. & Pursel, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test 221-T-18 scavenging of first-cycle waste

Description: The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.
Date: August 19, 1954
Creator: Schmidt, W.C. & Stedwell, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Probability of ruthenium reduction in H-4 by self-radiation

Description: The following calculations have been made at the request of H.R. Schmidt to determine the probability that self-radiation may play a substantial role in the decomposition of the ruthenium tetroxide in the reflux scrubber, section of the Redox Ruthenium Oxidizer (H-4). The validity of the derived data necessarily depends upon the correctness of the basic assumptions made with regard to process conditions and to possible radiation-activated mechanisms of disintegration. It is estimated that the e… more
Date: June 8, 1954
Creator: Upson, U. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Discussion of ruthenium problem in Redox Plant

Description: A meeting was held February 5, 1954 in the 2704-Z Building to discuss the ruthenium problem in the Redox Plant and to decide on a course of action to correct the problem. The following persons were in attendance.
Date: February 8, 1954
Creator: Mobley, W. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Essential material flow sheet of precipitation separations process

Description: This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, an… more
Date: August 19, 1954
Creator: Browne, W. G. & Murray, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nickel ferricyanide scavenging flowsheet for neutralized concentrated raw

Description: From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is poss… more
Date: October 26, 1954
Creator: Smith, R. E. & Coppinger, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test No. 105-565-A: Horizontal rod conversion---old piles

Description: In numerous instances the graphite growth in the older piles has deformed the horizontal control rod holes with a resultant jamming of the rods and overstressing of the rods and thimbles. In addition, special operating procedures to maintain very low differential pressures are required with the present allowed maximum graphite temperatures to prevent collapse of the thimbles because of loss of strength at this temperature. This is currently a limit to the power level of the H Pile. This report … more
Date: February 15, 1954
Creator: Call, R. L.; Rector, J. H. & Lovington, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A brief review of major problems at Redox

Description: During the last few months the Redox plant has been plagued with an excessive number of problems which have resulted in its inability to meet forecasted production schedules in November 1953, January and February 1954. The following paragraphs are intended to indicate some of the problems faced at Redox and the steps that are being taken to remedy them. It should be emphasized that the plant has been operating far above original design capacity and this fact tends to aggravate some of the probl… more
Date: March 2, 1954
Creator: Maider, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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