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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date:
December 9, 1963
Creator:
Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
System:
The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies
Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date:
September 1964
Creator:
Allemann, R. T.; Roberts, F. P. & Upson, U. L.
System:
The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3
This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date:
June 14, 1960
Creator:
Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System:
The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis
Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date:
February 1962
Creator:
Anderson, J. K. & Winegardner, W. K.
System:
The UNT Digital Library
Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date:
March 1961
Creator:
Baars, R. E.
System:
The UNT Digital Library
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Date:
June 2, 1960
Creator:
Batch, J. M. & Toyoda, K. G.
System:
The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford
Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date:
November 1961
Creator:
Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
System:
The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date:
September 1964
Creator:
Benham, R. D. & Wilburn, N. P.
System:
The UNT Digital Library
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date:
August 26, 1960
Creator:
Blaine, H. T.
System:
The UNT Digital Library
Construction Completion Report: CAI-816, 100-N Reactor Plant
Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date:
October 15, 1964
Creator:
Buckner, C. L.
System:
The UNT Digital Library
High Temperature Short-Time, Uranium Carbide-Metal Reactions
Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Date:
March 1963
Creator:
Christensen, J. A.
System:
The UNT Digital Library
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
Thermal Conductivity of UO2
Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date:
September 1962
Creator:
Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
System:
The UNT Digital Library
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date:
December 1962
Creator:
Defferdin, L. J.
System:
The UNT Digital Library
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962
Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date:
August 1962
Creator:
Doman, D. R. & Pankaskie, P. J.
System:
The UNT Digital Library
A Device for Recording Fuel Element Dimension on Punched Paper Tape
Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).
Date:
December 1962
Creator:
Driver, G. E.
System:
The UNT Digital Library
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Date:
July 1965
Creator:
Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
System:
The UNT Digital Library
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date:
July 18, 1960
Creator:
Frederick, C. L. & Waldkoetter, G. L.
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date:
March 1961
Creator:
Freshley, M. D.
System:
The UNT Digital Library
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date:
July 1964
Creator:
Godfrey, W. L. & Benham, R. D.
System:
The UNT Digital Library
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)
Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Date:
October 1963
Creator:
Hanford Atomic Products Operation
System:
The UNT Digital Library
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)
Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date:
October 1, 1963
Creator:
Hanford Atomic Products Operation
System:
The UNT Digital Library
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation
Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Date:
January 1964
Creator:
Hanford Atomic Products Operation. N-Reactor Project Section.
System:
The UNT Digital Library