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Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor

Description: Reactor physics studies in the Engineering Mockup Critical (EMC) assembly of the Fast Test Reactor (FTR) facility are reported. The study included measurements of the neutron spectrum, Doppler effect, sodium-void worth, reaction rates, subassembly worths, material replacement worths, and FTR control, safety and shim rod worths. Each of these physics studies were made in a clean plutonium (low-Pu-240) fuel composition environment and a dirty plutonium (high-Pu-240) fuel composition environment. … more
Date: July 1976
Creator: Pond, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Autoradiographic Technique for Rapid Inventory of Plutonium-Containing Fast Critical Assembly Fuel

Description: A nondestructive autoradiographic technique is described which can provide a verification of the piece count and the plutonium content of plutonium-containing fuel elements. This technique uses the spontaneously emitted gamma rays from plutonium to form images of fuel elements on photographic film. Autoradiography has the advantage of providing an inventory verification without the opening of containers or the handling of fuel elements. Missing fuel elements, substitution of nonradioactive mate… more
Date: October 1977
Creator: Brumbach, S. B. & Perry, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-240Pu Sector Experiments in ZPPR Assembly 4

Description: The complete high-plutonium-240 fuel experiment in ZPPR assembly 4 is reviewed. Results of criticality, enrichment, small-sample perturbation, sodium void, uranium-238 Doppler, control rod substitution and reaction rate measurements are presented. Comparison of these measured values with calculated results are included where possible. The relationship between the ZPPR high-plutonium-240 fuel experiments and the results obtained in previous critical experience is considered.
Date: December 1976
Creator: McFarlane, Harold F. & Beck, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance : Analytical: Answers to Specific Questions

Description: Eurochemic Assistance : Analytical requested answers to questions regarding the requirements for a combination control and development laboratory which is to be associated with a Purex-type solvent extraction processing plant. Personnel of the ORNL Analytical Chemistry Division replied to the questions.
Date: July 14, 1959
Creator: Corbin, L. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Facility for the Production of Pu238

Description: Abstract: A pilot plant facility for recovering Pu238 and unconverted neptunium from irradiated neptunium target elements was operated for 17 months at the Savannah River Laboratory. The process required that the irradiated target elements be dissolved and the solution be processed through three anion exchange cycles for removal of undesirable fission products and cations, recovery of unconverted neptunium, and concentration of Pu238 solution. The process equipment was enclosed in three stain… more
Date: September 1963
Creator: Tetzlaff, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963.

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 465 MWD/T during the quarter which brings the to… more
Date: April 8, 1963
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Staffing Experience for Operation of the Plutonium Recycle Test Reactor

Description: The Plutonium Recycle Test Reactor is a research and development tool supporting the Plutonium Recycle Program and the research activities at Hanford. The present organization directly associated with the PRTR is composed of Operating, Technical Assistance, Maintenance, and Engineering Groups. Liaison with research groups utilizing PRTR facilities is accomplished through the Technical Assistance Group. the other three groups serve the PRTR in the manner suggest by the group name. This paper … more
Date: September 23, 1963
Creator: Koberg, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactivity Control Problems in the Plutonium-Fueled EBR-1 Reactor

Description: In contrast with previous EBR-1 reactor cores which were fueled with enriched uranium, the current Mark IV core is a 7 x 8-in. cylinder made of delta-stabilized plutonium alloyed with 1 1/4 w/o aluminum. The reactivity of the reactor is largely controlled by the movement of the entire outer blanket mounted on a hydraulic elevator with a travel of 80 inches. Partial meltdown occurred in November, 1955 during the last experiment scheduled for the core which was directed toward identifying the tim… more
Date: October 1963
Creator: Haroldsen, R. O. (Ray Ottley), 1928-; McGinnis, F. D. & Smith, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Description: 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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Costs for a Plutonium Recycle System

Description: Report containing the estimated costs of the chemical and metallurgical steps in plutonium recycling for large desalination reactors.
Date: January 20, 1964
Creator: Harrington, F. E.; Arnold, E. D.; Brater, D. C.; Douglas, D. A.; Smiley, S. H.; Stockdale, W. G. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1963

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 831 MWD/T during the quarter which brings the tot… more
Date: July 15, 1963
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Designs and Special Applications for Fast Breeders

Description: The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy… more
Date: November 11, 1963
Creator: Hammond, R. Philip
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Cycle Plutonium Recovery by Amine Extraction

Description: The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble org… more
Date: May 24, 1961
Creator: Coleman, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Stainless Steels by HNO3-HF-AL(NO3)3 Mixtures During Evaporation of Plutonium Product Streams

Description: Corrosion studies on various stainless steels were carried out using aluminum ion as a fluoride complexing agent to minimize corrosive attack on the evaporator. The rate of corrosion of stainless steels during the evaporation of HF-HNO3 mixture is quite high even in the presence of excess aluminum. With two moles of aluminum ion per mole of fluoride ion, the corrosion rate of stainless steel types 329 and 309-Cb was approximately 30 to 40 mils per year. Corrosion rates of other type of stainles… more
Date: November 10, 1952
Creator: Arehart, T. A. & Runion, T. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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