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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
open access

Consolidated fuel-reprocessing program. Progress report, April 1-June 30, 1982

Description: Highlights of progress accomplished during the quarter ending June 30, 1982 are summarized. Discussion is presented under the headings: Process development; Laboratory R and D; Engineering research; Engineering systems; Integrated equipment test facility operation; Instrument development; and HTGR fuel reprocessing.
Date: September 1, 1982
Creator: Burch, W D
Partner: UNT Libraries Government Documents Department
open access

Decontamination of Cells 6 and 7, Building 3019, Following Plutonium- Release Incident

Description: As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating rea… more
Date: September 11, 1961
Creator: Parrott, J.R.
Partner: UNT Libraries Government Documents Department
open access

Remote equipment technology. Final report for GFY 1880

Description: An interactive graphics terminal and a desk-top computer were utilized to perform a Computer Aided Remote Maintenance simulation of a hypothetical equipment item. The equipment item included an electrical connection, hydraulic fitting, and simple bolt pattern which were maintained by remote manipulators during the simulation. These remote maintenance operations demonstrated that the Computer Aided Remote Maintenance simulation technology could be extended to complex equipment items. As a result… more
Date: September 1, 1980
Creator: Wadekamper, D. C.
Partner: UNT Libraries Government Documents Department
open access

HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 1

Description: Four runs were conducted in the Zirflex-Sulfex headend hot cell equipment. Prototype PWR blanket rods, Zircaloy2 clad UO/sub 2/, irradiated from 159 to 356 Mwd/t and decayed 2 years, were declad in boiling 6 M NH/sub 4/F-l M NH/sub 4/NO/sub 3/, terminating with a F/Zr mol ratio of 7 in the spent decladding solution. Average decladding time was 1.5 hr, leaving end cap residues of about 5 g per pin. At the end of the decladding, maximum loss of uranium and plutonium to the decladding solution was… more
Date: January 11, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
open access

MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960

Description: The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit… more
Date: September 30, 1960
Partner: UNT Libraries Government Documents Department
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Design features of the laboratory-scale radiochemical immobilization system

Description: Under the High-Level Waste Immobilization Program, the Pacific Northwest Laboratory (PNL) is studying various ways to solidify high-level nuclear wastes. A variety of waste forms and processes are being investigated, with the most highly developed process being spray calcination coupled with in-can melting. This report describes a remote laboratory-scale system that was designed for the purpose of investigating the effects of different operating conditions and waste compositions on the product … more
Date: May 1, 1980
Creator: Hanson, M.S.; Knox, C.A. & Berger, D.N.
Partner: UNT Libraries Government Documents Department
open access

RADIOISOTOPE TECHNIQUES FOR CHEMICAL, PHYSICAL, AND INDUSTRIAL APPLICATIONS

Description: A laboratory manual is given consisting of 14 experiments designed to teach some of the basic fundamentals of the application of radioisotopes, and to introduce the principles of radioisotope technology. The majority of the experiments, while designed to be practical, are planned for scientists having little background in radiochemical and radioisotopc technology, and the remainder are outlined for more advanced personnel. The experiments include isotope production, sample preparation and half … more
Date: September 1, 1961
Creator: Cassell, A.J.
Partner: UNT Libraries Government Documents Department
open access

ORNL shielded facilities capable of remote handling of highly radioactive beta--gamma emitting materials

Description: A survey of ORNL facilities having adequate shielding and containment for the remote handling of experimental quantities of highly radioactive beta-gamma emitting materials is summarized. Portions of the detailed descriptions of these facilities previously published in ORNL/TM-1268 are still valid and are repeated.
Date: September 1, 1977
Creator: Whitson, W. R.
Partner: UNT Libraries Government Documents Department
open access

SNAP Programs. Quarterly Progress Report No. 6, January 1 through March 31, 1961. Task 6. Fuel Technology Development Program

Description: Isotope power sources are being developed for use in thermionic and thermoelectric power generators for space applications. Suitable radioisotope fuels and heat source containment capsules are being designed for SNAP-type generators with land, sea and space applications. Curium242 and Plutonium-238 are currently being investigated, and methods for purification, compound conversion and fuel form are being established. A Heavy Elements Processing Facility capable of handling and preparing gram qu… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Apparatus for dynamic measurement of gases released from materials heated under programmed temperature-time control

Description: This apparatus, a prototype of one being constructed for hotcell examination of irradiated nuclear materials, measures dynamic release rates and integrated volumes of individual gases from materials heated under controlled temperature-time programs. It consists of an inductively heated vacuum furnace connected to a quadrupole mass spectrometer. A computerized control system with data acquisition provides scanning rates down to 1s and on-line tabular and graphic displays. Heating rates are up to… more
Date: April 1, 1982
Creator: Early, J.W. & Abernathey, R.M.
Partner: UNT Libraries Government Documents Department
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Investigation report of the release of strontium-90 from the Building 3517 Cell Ventilation Improvements construction site on November 29, 1985

Description: This Type B Investigative Report provides an evaluation of all relevant events and activities that led to, were an integral part of, and subsequently resulted from ORNL's November-December 1985 strontium-90 release incident. The impacts were evaluated in terms of radiological doses to ORNL and Rust employees associated with the incident, ORGDP employees who consumed potable water potentially impacted by the incident, and Kingston, Tennessee, residents who also consumed potable water potentially… more
Date: January 21, 1986
Partner: UNT Libraries Government Documents Department
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Experimental studies of actinides in molten salts

Description: This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen-containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of actinide elements and compounds, and measurements of v… more
Date: June 1, 1985
Creator: Reavis, J.G.
Partner: UNT Libraries Government Documents Department
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Design features of the radioactive Liquid-Fed Ceramic Melter system

Description: During 1983, the Pacific Northwest Laboratory (PNL), at the request of the Department of Energy (DOE), undertook a program with the principal objective of testing the Liquid-Fed Ceramic Melter (LFCM) process in actual radioactive operations. This activity, termed the Radioactive LFCM (RLFCM) Operations is being conducted in existing shielded hot-cell facilities in B-Cell of the 324 Building, 300 Area, located at Hanford, Washington. This report summarizes the design features of the RLFCM system… more
Date: June 1, 1985
Creator: Holton, L.K. Jr. (comp.)
Partner: UNT Libraries Government Documents Department
open access

WIPP conceptual design report. Addendum J. Support equipment in the high level waste facility of the Waste Isolation Pilot Plant

Description: The Aerojet Manufacturing Company (AMCO) received a contract in November 1976 to provide consulting services in assisting Holmes and Narver, Incorporated with the conceptual designs, cost estimates, and schedules of equipment used to handle waste casks, to decontaminate waste canisters and to overpack damaged or highly contaminated waste canisters for the Waste Isolation Pilot Plant (WIPP). Also, the layout of the hot cell in which canister handling, overpack and decontamination takes place was… more
Date: April 1, 1977
Creator: Rieb, M.J. & Foley, R.S.
Partner: UNT Libraries Government Documents Department
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Creep and cycling tests: thermal properties of Hanford concretes. [79 to 1175/sup 0/F]

Description: Four tests were conducted to determine thermal properties of concrete core material from the Purex Building at Hanford, Washington, and from concrete cast at the Portland Cement Association. Specific heat, thermal conductivity, and thermal diffusivity were measured as functions of temperature from 79 to 1175F.
Date: March 1, 1979
Creator: Gillen, M.
Partner: UNT Libraries Government Documents Department
open access

Consolidated fuel reprocessing program. Progress report, July 1-September 30, 1981

Description: Technical progress is reported in overview fashion in the following areas: process development, laboratory R and D, engineering research, engineering systems, integrated equipment test facility (IET) operations, and HTGR fuel reprocessing. (DLC)
Date: December 1, 1981
Partner: UNT Libraries Government Documents Department
open access

PROTEC TM TEAR-OFFS: RESULTS OF LONG TERM TESTING

Description: The Savannah River National Laboratory (SRNL) has completed a series of tests (Phases 1 and 2) to assess the potential use of a Mylar{reg_sign} tear-off system as a primary or secondary protective barrier to minimize acid etching ('frosting'), accidental scratching, and/or radiation damage for shielded cells, glovebox, and/or chemical hood windows. Conceptually, thin, multi-layered sheets of Mylar (referred to throughout this report as the ProTec{trademark} tear-off system) can be directly appl… more
Date: July 24, 2008
Creator: Peeler, D
Partner: UNT Libraries Government Documents Department
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324 and 325 Building Hot Cell Cleanout Program: Air lock cover block refurbishment

Description: The high-density concrete cover blocks shielding the pipe trench in the hot-cell air lock of the 324 Building Radiochemical Engineering Cells had accumulated fixed radioactivity ranging from 1100 to 22, 000 mrad/hr. A corresponding increase in the radiation exposure to personnel entering the air lock, together with ALARA concerns, led to the removal of the contaminated concrete surface with a hydraulic spaller and the emplacement of a stainless steel covering over a layer of grout. The resultan… more
Date: May 1, 1989
Creator: Katayama, Y.B.; Holton, L.K. Jr. & Gale, R.M.
Partner: UNT Libraries Government Documents Department
open access

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

Description: This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that … more
Date: October 1, 1991
Partner: UNT Libraries Government Documents Department
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Determination of nitride nitrogen in irradiated materials

Description: A method for determining nitride nitrogen was adapted for analyses of irradiated samples in a hot cell. Sections of stainless steel cladding material or fuel are dissolved remotely using various combinations of H/sub 2/SO/sub 4/, HCl, and HF. The nitrogen is separated from the highly radioactive sample solution by steam distillation using the Kjeldahl method. The collected distillates are moved from the hot cell to an open-front box where they are treated with Nessler's reagents for spectrophot… more
Date: March 1, 1979
Creator: Maez, M.A.
Partner: UNT Libraries Government Documents Department
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