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224-UA continuous calciner trough examination

Description: The continuous calciners at UO{sub 3} Plant are of a new design which was developed at HAPO and placed in service late in 1956. The heat transfer troughs are considered to be the most vulnerable parts of the calciners because of their high operating temperatures. Thermal stresses are calculated to be quite high, and when added to the direct mechanical stresses from powder load etc., come close to the limiting safe stress for stainless steel at the operating temperature. It is felt that trough f… more
Date: March 10, 1958
Creator: Kennedy, R. A.
Item Type: Refine your search to only Report
open access

234-5 Building RM line equipment tests, Task III mixer

Description: Several operations that are important to the process as carried out in Task III (Reduction) are performed by the mixer. In order to specify the process certain tests were made to study these operations and are discussed in this report. They include: Mixing Time, Mixer Discharge Rate, Mixer Holdup, and Mixer Capacity. A description of the test, conclusions and recommendations is provided.
Date: April 10, 1952
Creator: Collins, P. E.
Item Type: Refine your search to only Report
open access

234-5 Development Group - summary report, use of {open_quotes}AT{close_quotes} solution without evaporation

Description: A summary of work is presented from the 234-5 Development Group, September 1, 1950, with regard to the feasibility of transferring the plutonium processing solution, without evaporation, to the Purification Building. Critical factors identified were the concentration of the nitric acid and temperature.
Date: September 1, 1950
Creator: Lyon, W.L. & Facer, J.F.
Item Type: Refine your search to only Report
open access

300 Area ``X`` Program, Basis ``B``

Description: Attached is a secret draft of 300 Area expansion for the proposed ``X`` Program (600 MWD level for indefinite period) made up of the following: (1) assumptions; (2) present facilities and to what extent inadequate; (3) description of proposed work; (4) advantages to be gained and justification for proposed work; (5) why existing or alternate facilities cannot be used; (6) estimate of cost; and (7) attachments.
Date: March 14, 1952
Creator: Wood, V. W.
Item Type: Refine your search to only Report
open access

300-KV Pulser Transformer and Pulser.

Description: Photographs and working drawings are presented for a small (approximately 4.25 X 7 X 9 inch) 300Kv pulse transformer having double-conical secondaries each with a corona ring at its greatest diameter. The pulser circuit is shown but no text is included.
Date: November 1951
Creator: Heller, R. E.
Item Type: Refine your search to only Report
open access

327 Basin Aluminum Corrosion Test

Description: An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.
Date: February 9, 1956
Creator: Mallett, G. R.
Item Type: Refine your search to only Report
open access

450-Mev/C K$sup -$ and /Anti p/ Beams at the Northwest Target Area of the Bevatron Separated by the Coaxial Velocity Spectrometer

Description: Enriched beams of 450 Mev/c K/sup -/ mesons and antiprotons have been produced by separation with the coaxial static electromagnetic velocity spectrometer. Characteristics of the final separated beams as observed in the 15- inch hydrogen bubble chamber are given together with a detailed description of the beam optics and apparatas. (auth)
Date: June 1, 1958
Creator: Horwitz, N.; Murray, J. J.; Ross, R. R. & Tripp, R. D.
Item Type: Refine your search to only Report
open access

709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Item Type: Refine your search to only Report
open access

1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Item Type: Refine your search to only Report
open access

1706-KER Coolant Test Facility Operations Manual

Description: This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
Date: January 23, 1958
Creator: Dulin, R. V.
Item Type: Refine your search to only Report
open access

1953 at Hanford

Description: The report summarizes Hanford`s operation in 1953. The 38% increase in separated plutonium over the 1952 level was one measure of achievement. 1953`s output was more than seven times that of 1947, the first full year of General Electric`s operation of Hanford. Although much of this gain resulted from new reactors, some was due to improved safety devices, and much was due to increased knowledge of the controlling factors which permitted more efficient operation of old piles and better design of … more
Date: March 15, 1954
Item Type: Refine your search to only Report
open access

The 1A Hybrid Flowsheet

Description: A preliminary hybrid 1A flowsheet in which the extraction section operates substantially acid while the scrub section is acid deficient is presented. The effects of added nitric acid on the performance of the acid deficient 1A flowsheet are considered, and the need for control of the entering stream acidities in such flowsheets is evaluated. Data on batch-countercurrent decontamination and plutonium recovery are included. (J.R.D.)
Date: January 1, 1950
Creator: Coplan, B. V.; Davidson, J. K.; Hass, W. O. & Zebroski, E. L.
Item Type: Refine your search to only Report
open access

1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Item Type: Refine your search to only Report
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