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Radioactive contamination in the environs of the Hanford Works for the period April, May, June 1949

Description: This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works for the quarter April through June 1949. This belated document is issued for the records to fill in the gap for the quarterly reports not issued in 1949 because of personnel shortage at that time. Although the data summarized in this report were already reported in the H. I. Evirons Reports for the months involved, it is still of value to study the data combining the three months of d… more
Date: April 3, 1950
Creator: Paas, H.J. & Singlevich, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation control standards and procedures

Description: This manual contains the Radiation Control Standards'' and Radiation Control Procedures'' at Hanford Operations which have been established to provide the necessary control radiation exposures within Irradiation Processing Department. Provision is also made for including, in the form of Bulletins'', other radiological information of general interest to IPD personnel. The purpose of the standards is to establish firm radiological limits within which the Irradiation Processing Department will ope… more
Date: December 14, 1956
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination in the environs of the Hanford Works for the period October, November, December 1949

Description: This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works. The principal sources of the radioactivity originating as a result of operations at Hanford which affect the environment in this area are the two waste stacks in the separations area and the cooling water from the four pile areas. Measurements are also made on samples taken from the Hanford waste systems which are primarily confined within the project proper. Although monthly summari… more
Date: March 2, 1950
Creator: Paas, H.J. & Singlevich, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

G.E. Co. Hanford Works - Project C-431-A production facility - Sec. A, subcontract G-363, revised design report

Description: The 100-C project is to be located adjacent to the present 100-P Area. It is planned to build an addition to the present 181-B River Pump House using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and, therefore, protection against possible flood damage is assured.
Date: March 29, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Maximum temperature of aluminum end cap

Description: Neutron density at the end of the slug is increased appreciably and therefore the heat production in the end of the slug is also increased. The end result is increased heat flow into the cap with correspondingly higher temperatures. The combined results and conclusions of documents CP-1580, CP-1989, and CP-2871 afford a means of calculating the aluminum end cap temperatures with consideration being give to the above mentioned {open_quotes}Wilkins effect,{close_quotes} i.e., that the heat produc… more
Date: January 11, 1950
Creator: Roy, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Insulating webbing between thermal shield and graphite reflector

Description: The purpose of this document is to present the bases and calculations which resulted in the conclusion given in the letter of October 17. Also, the original calculations were made on the basis that the webbing face thickness is equal to 1/2 inch, which is no longer the case. The new thickness is 3/4 inch. This alters the condition of heat generation. Consideration is given to the heat generation in the legs.
Date: October 24, 1951
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pile graphite expansion

Description: The purpose of this memorandum is to present and analyze, in terms of the current status of knowledge of radiation damage to graphite, the data available at the present time on the expansion status of the graphite in the piles, and suggest, in terms of this analysis, several possibly feasible curative and preventive measures. The portion of the data to be covered in this memorandum consists of that obtained during the last four years from pile motion measurements and from tube bowing measuremen… more
Date: July 24, 1950
Creator: Warekois, E. P. & Reinker, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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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Pile Temperature Study

Description: Regarding heat transfer studies of annular spaces around the process tube, there is general agreement among all concerned, that high graphite temperatures are essential at the initial startup. Pile Technology, in studying graphite damage, has developed information that shows little or no expansion occurring when temperatures are maintained at 275{degrees}C. Stored energy levels are less than 5% and K/Ko has saturated in the region of 3.5 to 4. Badly expanded samples (1% increase in length) have… more
Date: January 17, 1950
Creator: Jaske, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination in liquid wastes discharged to ground at separations facilities through June 1956

Description: This document summarizes the amounts of radioactive contamination discharged to the ground from separation facilities through June 1956. Detailed data for individual disposal sites is presented on a month to month basis for the period July 1955 through June 1956. The major disposal sites in separation facilities, total volume of waste discharged at each location, and the gross amounts of plutonium and fission products discharged to the ground since startup are listed. This same data are present… more
Date: August 13, 1956
Creator: Heid, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recycle of 231 Building supernates to 224 T Building: Relationship to ``T`` and ``S`` Plant

Description: An examination of the process scheme for handling present and future 231 Building supernatant solutions is necessary to forecast the effects of placing one of the processing facilities (224B) in a standby status and to ascertain if rescheduling of any of the supernatant solutions to 202S will be necessary. The examination indicates the 231 Building process supernates and cell cleanouts together with the 221, 224T Buildings acid washes and the 234-5 Building returns can be processed through the … more
Date: August 20, 1952
Creator: Packer, G. V. & Schmidt, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Capacity survey -- Separations Division

Description: Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentrat… more
Date: June 28, 1951
Creator: Frame, J. M. & Tomlinson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design basis for proposed separations facility, for use in preliminary project proposal

Description: Members of the Working Committees for RDA DC-4 and RDA DC-7 (KE and KW Reactors) have reviewed and approved the design basis being used for the preparation of the 200 Area portion of the Program X preliminary project proposal. This design basis includes the following: plant capacity of 275 tons per month, average flow rate; the basic chemical process used will be the Purex process; the plant will be located in the Southeast Quadrant of the 200 East Area; the plant will contain a double line of … more
Date: March 17, 1952
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination in liquid wastes discharged to ground at separations facilities through December 1956

Description: This document summaries the amounts of radioactive contamination discharged to ground from separation facilities through December 1956. Detailed data for individual disposal sites is presented on a month basis for the period of July through December 1956. Previous publications of this series may be referred to for specific information on measurements and radioactivity totals prior to July 1956. Tables I and II list the major disposal sites in separation facilities, total volume of waste dischar… more
Date: February 19, 1957
Creator: Heid, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Authorization for change in operating standards, 221 and 224 Building, pertaining to process changes during the period March 1, 1951--December 1, 1952

Description: Since the issuance of HW-17398, Separations Section Operating Standards - Part I relating to the Bismuth Phosphate Process on March 1, 1951, several changes in the process have been found desirable and have been reduced to practice. This document presents these changes.
Date: December 2, 1952
Creator: Bailor, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Laboratory evaporation of Redox PR solution

Description: Since Redox start-up, several samples of Redox PR solution have been evaporated in the laboratory as one step in a study of the Redox -- 234 coupling process. Because feed for Task I in 234-5 will be produced by evaporative concentration of Redox and purex product solutions, and because laboratory work has shown the desirability of filtering Redox solutions after such evaporation prior to use in Task I. This report summarizes the observations which have been made in the course of this work, as … more
Date: April 3, 1953
Creator: Beede, R. L.; Facer, J. F. & Pugh, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation intensity at center 42 inch riser on waste storage tank (MJ-4)

Description: It is recommended that the actual intensity existing today above the liquid be measured before recommendations are made on cutting through the concrete seal. A detailed statement of work on this problem follows. The calculations have been filed. In the study of the feasibility of cutting through the concrete seal on the center riser of the waste storage tank the radiation intensity that would be encountered is critical because director operator contact would be required. The question of the rad… more
Date: February 17, 1950
Creator: Weeks, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

{open_quotes}O{close_quotes} ring sealed process tube, Phase II, test project

Description: The {open_quotes}O{close_quotes} ring seal has been proposed to replace the van stone flange and the bellows thermal expansion assembly currently used on the existing Hanford piles to achieve water and gas seals, respectively. Possible advantages of the {open_quotes}O{close_quotes} ring seal are: (1) simplification of component parts and elimination of van stone corrosion; (2) simplification of maintenance; (3) lower costs of initial erection; (4) increased strength. This test supplements Test … more
Date: April 9, 1951
Creator: Johnson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design criteria - slug assembly and quench machine

Description: Mechanization of the 300 Area slug canning facilities is required to obtain uniform high quality product and to eliminate variables introduced by the human element. The work to be covered by this brochure will cover requirements for mechanization of only the operations occurring within the aluminum-silicon canning bath: can and cap preheating and wetting, canning assembly, and quenching operation. Briefly, this machine will be required to insert a prepared uranium slug into an aluminum can and … more
Date: November 27, 1951
Creator: Blanton, W. A.; Smith, E. A. & Shaw, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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