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Status of plant assistance irradiations as of July 16, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. … more
Date: August 3, 1965
Creator: Ferguson, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status report of confinement studies Douglas United Nuclear operated reactors

Description: Confinement studies on the Hanford Production reactors were started in March at the request of the Richland Operations Office. The confinement studies were then undertaken with the following objectives established: (1) review and reestablish if necessary, the maximum credible accident for the production reactors operated by Douglas United Nuclear (DUN); (2) evaluate the present confinement systems under the Code of Federal Regulation Title 10, Part 100, Reactor Site Criteria, for the maximum cr… more
Date: November 30, 1965
Creator: Spink, J. R. & Fifer, N. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production Test IP-719: The effect of water plant variables on effluent activity. Final report

Description: One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter… more
Date: February 23, 1965
Creator: Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

K Area Hot Test Hole Temperatures

Description: This report details a K area test with the following objectives: find the temperature range within a graphite sample carrier; find the temperature range with a solid graphite bar; find the temperature range with a test hole; determine the temperature difference between the old and new graphite sample boats; compare the temperature of a sample load and a solid bar in the same location; and find the temperature range in which the graphite samples are irradiated in all test holes. Results and conc… more
Date: August 4, 1965
Creator: Cox, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research and Engineering Operation, Irradiation Processing Department monthly record report, May 1965

Description: Process and development activities reported include: depleted uranium irradiations, thoria irradiation, and hot die sizing. Reactor engineering activities include: brittle fracture of 190-C tanks, increased graphite temperature limits for the F reactor, VSR channel caulking, K reactor downcomer flow, zircaloy hydriding, and ribbed zircaloy process tubes. Reactor physics activities include: thoria irradiations, E-D irradiations, boiling protection with the high speed scanner, and in-core flux mo… more
Date: June 4, 1965
Creator: Ambrose, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Release of radioactivity to the Columbia River from irradiated fuel element ruptures

Description: McCormack and Schwendiman issued a report in 1959 which estimated the amount of fission products from fuel element failures entering the Columbia River during the period 1952--1958 inclusive. Since that time there have been no attempts made to publish similar information for the subsequent years. It is the purpose of this report to review the fuel element rupture experience of 1964 as somewhat typical of the last few years, and to estimate the amount of significant fission products which entere… more
Date: May 27, 1965
Creator: Jerman, P. C.; Koop, W. N. & Owen, F. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conversion ratio tables

Description: This manual provides a list of the quantities of plutonium and plutonium isotope formation. Other isotopes whose concentrations are important and included in this report are U-236 buildup, U-235 burnout, U burnout, Np-237 build-up, GVR (the Gas Volume Ratio) in coproduct target elements and equivalent gram of plutonium. These conversion tables have been calculated on the IBM 7090 digital computer using a program entitled ``FLEX-3.`` The results of the computer solutions have not been normalized… more
Date: July 2, 1965
Creator: Chitwood, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of plant assistance irradiations as of April 9, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of material undergoing irradiation awaiting dispositions material shipped during the months and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, ``Status Report Equations.`` The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure re… more
Date: April 23, 1965
Creator: Ferguson, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical feasibility of using uranium oxide fuels at Hanford

Description: The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated valu… more
Date: February 15, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pacific Northwest Laboratory monthly activities report, April 1965

Description: This report discusses research at the Pacific Northwest Laboratory on topics relating to hanford production reactors. The topic deal with: reactor and material technology; reactor physics and instruments; chemistry; biology and medicine; applied mathematics; radiation protection; and test reactor and engineering services.
Date: May 14, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary investigation of water coagulation characteristics as affects reactor effluent radionuclides

Description: Several theories have been advanced regarding the structure and characteristics of the aluminum hydroxide molecule when produced from alum in the water treatment process. The Water Treatment Task Force initiated this test to exploit a theory that increased adsorption of soil-leached elements, present in Columbia River water, by the floc particle would occur when the precipitate vas formed in its terminal pH state. This report discusses a half-plant test which was initiated at E Reactor Plant wh… more
Date: April 15, 1965
Creator: Frymier, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim report II: Production test IP-634, half-plant low pH test water treatment at D Reactor process tube examination results

Description: Two half-plant tests were conducted at D reactor to evaluate the effect of process water pH on corrosion of aluminum process tubes and fuel elements. The first test demonstrated that a reduction in coolant pH from 7.0 to 6.6 reduced aluminum corrosion by a factor of between 2 and 3. Fuel weight loss data from the second test indicated that reducing coolant pH from 6.6 to 6.2 would result in an additional factor of 2 to 3 reduction in aluminum corrosion. This report presents the results of ex-re… more
Date: January 1, 1965
Creator: Hough, C. G. & Paglieri, J. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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