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PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JUNE 1959

Description: 8 5 F 5 ; 9 6 9 7 4 / 1 < =15% cold-worked Zircaloy-2 at 290, 345, and 400 deg C is being continued. Research to identify factors affecting irradiation-induced volume changes in graphite by means of sink- float density measurements was oontinued. The program to simulate conditions after a postulated loss-of coolant incident within the PRTR was completed. Lapsed-time motion pictures are being made through a windowed autoclave of the corrosive action of high-temperature water on defected Zircaloy2 U specimens. Progress on the development of an isotopic-exchange leak-detection systems is summarized. A program to develop a thermal-neutron-flux munitoring system for the Hanford reactors is reported. A project is being conducted to determine the temperature and approximate composition of the ternary eutectic in the Al--U--Ni alloys. A feasibility study to determine if Ca coatings can be successfully put on Ni by arc-spraying methods is reported. Work was continued on the valence effects of oxide additions (CaO and La/sub 2/O/sub 3/) to UO/sub 2/. An investigation is being made of the effects of combined high pressure and temperature on UO/sub 2/. Postirradiation data are presented on fueled specimens of ZrH/sub 1.65/--2 wt.% U. An evaluation of the effect of irradiation on the mechanical properties of AISI Type 347 stainless steel is being conducted. Hothardness data are presented for high-purity Nb, Nb-- Zr, Nb-V, Nb-Ti, Nb-Fe, Nb-Cr, Nb-V-Ti, Nb-V-Mo, Nb-V-Fe, Nb-V-Cr, Nb-V-Al, Nb-Zr-V, Nb-ZrTi, Nb-Zr-Mo, Nb-Zr-Cr, and Nb-Zr-Fe. A summary is presented of corrosion results obtained on Nb, Nb-Zr, Nb-W, Nb-Mo, Nb-V, Nb-Fe, Nb-Ti, Nb-Ti-Cr, Nb-Ti-Mo, and Nb-Ti-V alloys exposed in high-temperature water and steam. Corrosion data are given for Nb-U alloys in air, CO/sub 2/, NaK, water, and steam. Techniques are being developed for the preparation and cladding of cermets containing 60 to 90 vol.% of fuel dispersed in ...
Date: July 1, 1959
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Partner: UNT Libraries Government Documents Department

Four in. three jaw type connector suitable for vertical mounting sample for job 11

Description: As authorized by purchase order No. 11-2532 dated March 11, 1949 of the Kellex Corp., the first sample of a 4 inch three jaw type connector for Job 11 was fabricated. The design of the connector was per Crane Co. drawing DR-25126-D except vertical mounting. The materials were per Crane Co. drawing A-24491-C. As instructed in verbal conversation with Dr. D.D. Jacobus and as requested in Mr. J.J. Cuniffe`s letter of May 6, 1949, and Ingersoll-Rand Company`s 1 1/4 inch 534 impact wrench with suitable socket to fit the hexagon head of the operating screw of the 4 inch connector was procured on loan to make some preliminary tests. Engineering drawings are listed in a second report on the data base.
Date: July 8, 1949
Creator: Grubbe, A.C.
Partner: UNT Libraries Government Documents Department

ARCHITECTURAL AND CIVIL STANDARDS

Description: Hanford Atomic Production Operation specification guides and standards for architectural and civil engineering are presented. Information includes construction of roads, railroads, roofs, signs, buildings, building equipment, sewers, fences, safety systems, and drainage systems. Details of this manual are given in TID-4100 (Suppl.). (N.W.R.)
Date: January 1, 1963
Partner: UNT Libraries Government Documents Department

A FUEL REPROCESSING PLANT FOR FAST CERAMIC REACTORS

Description: A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. (auth)
Date: February 1, 1962
Creator: Alter, H.W.
Partner: UNT Libraries Government Documents Department

Study of the effects of a disaster at Grand Coulee Dam upon the Hanford Works

Description: Declassified 23 Nov 1973. It is assumed that the Grand Coulee Dam would be destroyed by one direct hit following detonation of an atomic bomb. Major effects of the explosion include flooding and isolation of Richland, flooding of Midway Substation, and flooding of surrounding areas. Maximum water elevations following a direct hit and indirect hits are estimated. Data are presented for flow through openings and flow through dam failure. (HLW)
Date: February 1, 1950
Creator: Kramer, H.A.
Partner: UNT Libraries Government Documents Department

Westinghouse Hanford Company (WHC) standards/requirements identification document (S/RID)

Description: This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES&amp;H) standards/requirements for Westinghouse Hanford Company Level Programs, where implementation and compliance is the responsibility of these organizations. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.
Date: March 15, 1996
Creator: Bennett, G.L.
Partner: UNT Libraries Government Documents Department

Hypothesis concerning irradiation embrittlement of uranium

Description: In discussions with a number of people, a hypothesis has been evolved which appears to fit available information concerning irradiation embrittlement of uranium as well as indicate a possible solution to the problem. The purpose of this memorandum is to expound this hypothesis as an aid to those working with the problem. Since it embodies the ideas of many people, no claim to unique authorship is implied.
Date: April 7, 1955
Creator: Wood, E.C.
Partner: UNT Libraries Government Documents Department

Material balance flowsheet Redox Production plant

Description: The attached material balance flowsheet for the proposed Redox Production plant is based on the two chemical flowsheets submitted by R.B. Richards of the Technical Division in HW 13,320 (INDC-3130) and HW 13,452 (INDC 3176). Production rates for the plant have been assumed as 2.5 short tone U per day (including a maximum of 0.75 short tons of U from stored Bi PO{sub 4} waste) and 19 kg. Pu per month (633 gms/day) as established by the Redox Committee. The flowsheets for preparation of solvent extraction feed from Bi PO{sub 4} waste, as well as the waste treatment systems will be covered in a future document.
Date: June 6, 1949
Creator: Tomlinson, R.E.
Partner: UNT Libraries Government Documents Department

Geochemical variation of Columbia River basalts beneath the Hanford Reservation, Washington

Description: Major element and trace element analyses of Columbia River basalts have been compiled to indicate where geochemical changes occur in the stratigraphy of the basalts. The analyses were averaged and plotted on petrologic variation diagrams to elucidate geochemical trends and correlations. This report is concerned mainly with the major elements. (auth)
Date: September 30, 1972
Creator: Tatman, J.B.
Partner: UNT Libraries Government Documents Department

Hanford radiochemical site decommissioning demonstration program

Description: A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given. (JSR)
Date: August 1, 1971
Creator: Nelson, D.C.
Partner: UNT Libraries Government Documents Department

Classified information required by operators and others exposed to radiation hazards

Description: Information required by operators exposed to radiation hazards is discussed. All areas of the plant are subjected to radiation hazards similar to those in the radium industry. Personnel in these areas are required to wear pencil meters and special badges that are evidently not solely for identification. They are required to submit to medical examinations more stringent and frequent than usual. They are required to wear heavy gloves in one location, thin gloves in another, disposable hats or rubbers in another. They are required to stay away from familiar objects that they could handle a few days before. They observe health instrument men making readings at points not tangibly influenced by the operations. Under these circumstances, operators cannot perform their duties intelligently without being advised of the general nature of the risks involved. Since the general beta and gamma hazard occurs at nearly all points and cannot reasonably be concealed, this is the feature selected for general information. The special hazard of 105 Building can then be concealed, and the origin, but not the nature of the hazard in 231 likewise concealed.
Date: August 31, 1944
Creator: Parker, H. M.
Partner: UNT Libraries Government Documents Department