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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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The Effectiveness of Spray Cooling

Description: Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was… more
Date: October 1, 1953
Creator: Dayton, R. W.; Allen, C. M. & Miller, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of reactor effluent water as steam plant boiler feed

Description: The radiological aspects of a proposal to recover some of the heat now wasted in cooling water from the Hanford reactors by using the hot water as boiler feed for the steam plants in the 100 Areas are evaluated. The radioactive material in the hot effluent water will contaminate the boiler feed water system, cause additional radiation exposure of personnel, and increase the cost of maintenance and radiation protection, but very little radioactive material will be carried over into the steam sys… more
Date: December 8, 1953
Creator: Clukey, H. V.
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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The use of aluminum sulfate for 100 Areas' process water coagulation

Description: Increases in power levels of the Hanford Piles have resulted in increased demands for process cooling water to the extent that the present filter plants are now operating at or above their design capacity. Further power level increases requiring even more cooling water may demand the operation of the filters considerably above design capacity. It has been proposed that by the use of aluminum sulfate, or filter alum, as a process water coagulant and activated silica as a coagulation aid, the pre… more
Date: January 4, 1952
Creator: Woods, W.C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The effects of water quality on pile operation

Description: Tests have been made to study the effects of lowering process water pH from pH 7.7 to the range pH 6.2--7.3; of reducing the amount of sodium dichromate inhibitor added to the water; and of eliminating the filtration step in the water treatment process. The results on the pH testing showed that reducing the pH of the cooling water would reduce aluminum corrosion rates. The plant specification has been changed to lower process water pH from 7.7 to 7.3 and plant scale testing of pH 7.0 water is i… more
Date: September 23, 1955
Creator: Miller, N.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical activities report on Hanford water studies

Description: This report is a comprehensive study of the cooling water systems for Hanford production reactors. It includes: film formation study, water plant flow improvement study, water quality tests, sodium dichromate elimination tests, corrosion in aluminium coagulated water study, and water composition, film formation, and effluent activity relationships. A section on special water studies is also included. 22 figs., 25 tabs.
Date: April 1, 1952
Creator: Fryar, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas cooling of cylindrical control rods for pile Area ``G``: Preliminary report

Description: A first approximation of the gas required to cool control rods for Pile Area G is presented in the following report. Since the results are based on a number of assumptions and approximations, they should be considered only as a first approximation and subject to revision. A gadolinium-stainless steel control rod can probably be readily cooled by gas. A boron-stainless steel control rod would be difficult to cool with gas and would probably require about 1,000 lbs./hr. of helium per rod. Carbon … more
Date: March 23, 1950
Creator: Robbins, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tentative design basis new 100 Area water plant embodying a close cooling water circuit

Description: The attached document includes a plot plan, flow diagram and delineation of basic assumptions upon which the report was developed. It summarizes the work which has been accomplished to date under RDA No. DC-6 in developing a recirculating water system to serve a new reactor. In order to proceed with the work under RDA No. DC-6 it has been necessary to make certain basic assumptions relative to the primary circuit requirements of RDA No. DC-3. These assumptions are explained in the report and ar… more
Date: November 14, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Appendix to HDC 2118 design criteria 100-X reactor water plant, general description - section II

Description: The factors responsible for the advances of 100-X compared with the older areas are: Simplification of the process, such as elimination of separate process water clearwells, by having the filtered water reservoirs perform that function. Combination of separate buildings into one building, such as combining filter pump house and process pump house. Use of electric standby. Use of higher capacity pumps and filter basins, and so fewer number of units. Centralization of control and operation. More … more
Date: March 29, 1952
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bibliography

Description: From abstract: This bibliography consists of references pertaining to "Effects of Nuclear Radiation Upon Electronic and Electrical Components", and to "Electronic and Electrical Components for Critical Environments". References were compiled from the Classified and Unclassified report literature and the published literature. The following indexes and abstract journals were used: Weapons Data Index, AEC Card Catalog, Engineering Index (1950-55), and Office of Technical Services, Research Reports… more
Date: April 30, 1957
Creator: Frost, Frederick E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactive Waste Processing and Disposal (1950-1957): Bibliography

Description: From abstract: "This bibliography consists of reports compiled from the AEC Library Card Catalog. Only the Classified and Unclassified report literature is included. For the published literature the reader is referred to an unpublished paper by V. Carson (UCRL - Livermore Library)" titled "Radioactive Waste Disposal" (April 25, 1957). "All progress reports covering the work have been omitted in order to exclude a large amount of duplicate information which is usually found in more detail in top… more
Date: May 6, 1957
Creator: Frost, Frederick E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Existing reactor expansion study basis

Description: The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to pro… more
Date: June 24, 1959
Creator: Heacock, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Expansion of Hanford Works facilities

Description: This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which th… more
Date: June 28, 1951
Creator: Parker, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The use of ALUM and activated silica for 100 Area process water coagulation. Final report

Description: Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process,… more
Date: July 15, 1955
Creator: Woods, W. C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reduction of rear face Zn{sup 65} activity

Description: This report discusses two methods which have been considered to reduce the rear face activity. The first involves the use of a solids purge to scour out the activity, and the second employs the use of a chromic acid purge to put the activity into solution. Solids purging is found to be ineffective in reducing rear face activity levels. A chromic acid purge conducted at 60 C for 1/2 hour can be expected to reduce the Zn{sup 65} activity level about five fold without injuring the reactor or causi… more
Date: January 31, 1955
Creator: de Halas, D. R. & Gay, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Study of the Pile Effluent Piping System

Description: In order to carry out the program of increased pile operating levels either tube outlet temperature or the water flows must be increased. This program proposes a considerable increase in both the pile effluent water flow and temperature. Consequently an investigation was started of problems that might be encountered in the pile effluent system. Later, a decision was made that the portion of this investigation dealing with the effects of increased water flow would be handled by the Pile Material… more
Date: October 20, 1953
Creator: Jones, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress Analysis of Bulk Effluent System Components in B and C Reactors

Description: This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.
Date: July 10, 1958
Creator: Adams, O. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GEH-4-32, Bonded segmented fuel element irradiation

Description: We have prepared what we call a bonded segmented fuel element. This fuel element has characteristics which make it an attractive prospect for high specific power operation at relatively low uranium temperatures. The fuel slug is made up of six longitudinal segments; each segment being bonded to the aluminum webbing and tubing that encases it. The pertinent information for this irradiation is summarized along with fabrication details and hazards, thermal aspects and calculations, and figures.
Date: September 16, 1958
Creator: Neidner, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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