Technical Report Archive & Image Library (TRAIL) - 109 Matching Results
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- Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process
- Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.
- Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process
- Report that summarizes the design work of the radioactive chop-leach demonstration at the Idaho Chemical Processing Plant presented in two parts.
- Proposal for an Advanced Engineering Test Reactor : ETR II
- Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
- MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650
- Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
- Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office
- Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
- Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office
- Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
- Standard Practices for Design of MTR and ETR Safety Circuits
- Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
- Supplement to Standard Practices for Design of MTR and ETR Safety Circuits
- Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
- Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO
- Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
- Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
- Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
- A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
- Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
- An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
- Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
- Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels
- Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
- Critical Path Scheduling of ETR and MTR Reactor Shutdowns
- Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
- Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors
- Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.
- ICPP Waste Calcining Facility : Safety Analysis Report
- Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
- Zirconium Processing Capability of the Idaho Chemical Processing Plant
- Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
- A Preliminary Report on the MTR Crystal Spectrometer
- Report regarding the installation and testing of a neutron crystal spectrometer. This was part of a slide show presentation.
- The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources
- Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).
- MTR Technical Branch Quarterly Report, Third Quarter
- Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
- Chemical Processing Instrumentation and Control Research Program
- Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
- Design Bases for ICPP Waste Calcination Facility
- Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
- Research and Development Studies on Waste Storage Process
- Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
- Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
- Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
- Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho
- Report that "summarizes the costs, experience and results of contracts AT(10-1)-1054 and AT(10-1)-1122 for drilling, casing and cementing observation wells at the National Reactor Testing Station, Idaho" (p. [11]).
- Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue
- Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
- Summary of the Spert-I, -II, and -III reactor facilities
- Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
- Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I
- Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
- Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide
- Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
- Maintenance of ETR Coolant
- Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
- Standard Practices Guide for Writing Experimental Operating Manuals
- This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
- ETR Nuclear Instrumentation : Final Report
- Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
- Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office
- Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
- Experimental Organic Cooled Reactor : Conceptual Design
- Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
- The Design, Installation, and Testing of the Gas-Cooled Reactor UO₂ Irradiation Experiment at the NRTS
- Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
- U.S. Atomic Energy Commission Idaho Operations Office Health and Safety Division Annual Report: 1961
- Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
- Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
- Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
- Instrumentation and Control Practices in U.S.A. Reprocessing Plants
- Report surveying the "[i]nstrumentation and control practices at the Hanford Plant, the Idaho Chemical Processing Plant, the Oak Ridge national Laboratory, and the Savannah River Plant" (p. iv).
- Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
- Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
- Chemical and Physical Character of Ground Water in the National Reactor Testing Station, Idaho
- Report documenting "the chemical and physical properties of the ground water beneath the National Reactor Testing Stations (NRTS), Idaho. The chemical properties described are chiefly the concentration and proportions of the dissolved constituents" (p. 1).
- Special Power Excursion Reactor Test III Pressurizer Vessel Failure
- Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
- Topic: a Fortran Program for Calculating Transport of Particles in Cylinders
- Report discussing the use of TOPIC Sn computer code in the attempt to find a solution to the Boltzmann transport equation.
- Annual Progress Report on Fuel Element Development for Fiscal Year 1961
- Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
- Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
- Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.