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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: 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.
Item Type: Refine your search to only Report
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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Item Type: Refine your search to only Report
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Some Considerations on the Configuration and Stability of the H2 Temperature Control Loops of the 80" Bubble Chamber

Description: There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression fo… more
Date: January 7, 1964
Creator: Androulakis, John G.
Item Type: Refine your search to only Report
open access

Biological Effects of Thermal Neutrons and the B10 (n,c) Li7 Reaction

Description: Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a… more
Date: January 13, 1964
Creator: Archambeau, J. O.; Alcober, V; Calvo, W. & Brenneis, H.
Item Type: Refine your search to only Report
open access

Dose-survival Curves for HeLa Cell Cultures Using Thermal Neutrons and the B10 (n,α)Li7 Reaction

Description: The biological evaluation of the thermal neutron capture reaction of boron-10, B10 (n,α)Li7 + 2.786 MeV, has previously been studied, using different particles from the boron-10 thermal neutron capture reaction compared with 250 kvp x-rays has been reported as 1.05 for spleen-thymic weight reduction (1), as 1.5 to 2.0 for skin lesions in pigs (2), and 1.87 for skin lesions of the rabbit's ear (3). The significance of such a calculation is felt to be unreliable for the boron-10 reaction in anima… more
Date: January 13, 1964
Creator: Archambeau, J. O.; Drew, R. M. & Robertson, J. S.
Item Type: Refine your search to only Report
open access

Subsurface Fracturing from Shoal Nuclear Detonation: Final Report

Description: Abstract: A fracture-evaluation experiment in conjunction with the Shoal nuclear detonation in granite was undertaken to determine the extent of subsurface shock-induced fractures. Preshot and postshot geophysical logs in a hole drilled from the surface through the zone of fractures indicated that fractures extended at least 5.3 cavity radii laterally from the point of detonation. Quantitative measurements of permeability increases resulting from the detonation were planned, but were not comple… more
Date: June 1964
Creator: Atkinson, Charles H.
Item Type: Refine your search to only Report
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: July 15, 1964
Creator: Auleta, J. J.
Item Type: Refine your search to only Report
open access

Ichiban: The Dosimetry Program for Nuclear Bomb Survivors of Hiroshima and Nagasaki - A Status Report as of April 1, 1964

Description: From Abstract: "The approach to the problem has been as fundamental as possible with emphasis on quantitative measurements and calculations of the energy, angular, and spatial distributions of weapons radiations in an air-over-ground geometry. Spatial distributions of dose in various shields, including Japanese dwellings, have been measured. Techniques have been developed in Japan for verifying the location of survivors and accurately describing their shielding environments."
Date: April 1964
Creator: Auxier, J. A.
Item Type: Refine your search to only Report
open access

Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Item Type: Refine your search to only Report
open access

Study of EOCR Modifications for Testing Fast Reactor Fuels

Description: Report issued by the APDA over studies conducted on "methods for increasing the power generation in a fast reactor fuel element test sample" (p. 9). The methods investigated are presented and discussed. This report includes tables, and illustrations.
Date: February 17, 1964
Creator: Ball, G.; DeFelice, J.; Edwards, J. J.; Jens, W. H.; Kovac, L. R.; Poggi, R. et al.
Item Type: Refine your search to only Report
open access

General Description of the 80" Bubble Chamber Refrigeration System

Description: Reliability of individual components and the ability to produce refrigeration even if one or two of these components should be in operable are the prime design parameters of this cycle. Each component was looked at with these two parameters in mind and any item that had obvious objections was either rejected or backed up with another piece of equipment. Along this line, you will notice (refer to line schematic) two hydrogen compressors and two nitrogen compressors; for full capacity all are req… more
Date: January 7, 1964
Creator: Bamberger, J. A.; Brown, D. P. & Jensen, J. E.
Item Type: Refine your search to only Report
open access

Hydrogen Refrigerator Design Capacity for 80" Chamber

Description: When the design of the refrigerator was begun, one of the important parameters was refrigeration capacity required. In order to estimate the required hydrogen refrigeration load the following had to be considered: 1. Dynamic Load due to pulsing of the chamber. Although this has been determined some two years ago through test work, it has not been published as of this date and will be presented here. 2. Static losses due to conduction, radiation, and convection. This is covered by Eng. Note BC-0… more
Date: January 7, 1964
Creator: Bamberger, J. A.; Brown, D. P. & Jensen, J. E.
Item Type: Refine your search to only Report
open access

Final Report: The Cesium-137 Power Program

Description: From introduction: The technology of isotopic power generation, though recent, is a logical extension of the search for power from the atom. Controlled fission of uranium utilizes only a fraction of the total energy made available from this nuclear process.
Date: May 1964
Creator: Banks, Hampden O., Jr.
Item Type: Refine your search to only Report
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