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Parameters of the 132 eV Neutron Resonance in Co 59
An accurate determination of the parameters of the resonance excited by the interaction of the 132 eV neutrons with the Co 59 target nucleus has been made, using the fast choppers at Brookhaven National Laboratory in the United States and Chalk River Laboratory in Canada. Neutron transmission through thick and thin samples resulted in the following parameters: [parameters not transcribed]. In addition, measurements of the resonance capture γ-ray intensity gave the value for the radiation width Γγ= 0.40 ± 0.04 eV, based on the known thermal capture cross section of cobalt of 37.5 barns. The reduced and total resonance capture integrals are calculated from the above parameters to be 50.5 ± 5.5 and 67.0 ± 5.5 barns, respectively. The above results are compared with previously determined resonance parameters and also with direct measurements of the total resonance capture integral.
Date:
March 25, 1963
Creator:
Jain, A. P.; Chrien, R. E.; Moore, J. A. & Palevsky, H.
Object Type:
Report
System:
The UNT Digital Library
Effects of Low Levels of X-Rays and Irradiation from C14 and H3 on Cell Population Kinetics in the Root Tip of Tradescantia
Reciprocal labelling in double-labelling experiments with H3- and C14- thymidine showed that when H3- thymidine (1μc/ml for 0.5 hr) was given first in the labelling sequence followed by a 4 hr interval before the C14- thymidine treatment, that passage of cells into and out of DNA synthesis was normal. When C14 was first in the sequence, the rate at which cells entered DNA synthesis was decreased. This was attributed to a radiation effect produced by the β-rays from the C14. The rate at which cells entered DNA synthesis was studied after 0.1, 1 and 10 rads of x-rays. A dose of 1 and 10 rads decidedly depressed the rate. Treatment of roots with 2, 20, and 200 μc/ml of tritiated water for 0.5 hr showed that the 2 higher concentrations produced an effect similar to the x-rays. This indicated that somewhere between 1 and 8 disintegrations per cell per 0.5 hr will produce a decrease in the rate at which cells enter DNA synthesis. In both the x-ray and H32O experiments the depression of the rate that cells entered DNA synthesis seemed to reach saturation at the higher doses.
Date:
March 25, 1963
Creator:
Wimber, Donald E.
Object Type:
Report
System:
The UNT Digital Library
Memorandum
We have recently completed measurement of resonance escape probability in the BNL reactor and in several slightly-enriched uranium light water moderated lattices. In addition, WAPD has made available to us data from other slightly enriched uranium-water lattices, so that about 18 lattices in all have been done.
Date:
June 25, 1956
Creator:
Sher, R.
Object Type:
Report
System:
The UNT Digital Library
Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices
The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solution of the transport equation such as the P1 and P3 solutions.
Date:
May 25, 1959
Creator:
Nilson, R. & Oakes, T. J.
Object Type:
Report
System:
The UNT Digital Library
Random Loading of E-Metal Dissolver
Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid rods as well as I. and E. fuel having a 1.37-inch O.D. by a 0.48-inch I.D. have already reported.
Date:
February 25, 1959
Creator:
Ketzlach, M.
Object Type:
Report
System:
The UNT Digital Library
Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.
The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected that the reactor operations and radiation monitoring personnel will implement these instructions according to standard operating procedures.
Date:
February 25, 1959
Creator:
Crossman, W.A.
Object Type:
Report
System:
The UNT Digital Library
Hastelloy F Dissolver Installation in 321 Building
Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered during the fabrication of the vessels.
Date:
May 25, 1959
Creator:
Cooley, C. R.
Object Type:
Report
System:
The UNT Digital Library
Artificial Cooling of the Columbia River By Dam Regulation Part 1
In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date:
May 25, 1959
Creator:
Kramer, H. A.
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Nuclear Materials Content of Non-Production Fuels
In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date:
May 25, 1959
Creator:
Schneider, R. A.
Object Type:
Report
System:
The UNT Digital Library
Report of Invention The Preparation of Uranium Dioxide by Fused Salt Electrolysis
This is a report of what may be an invention in the preparation of uranium dioxide of a quality particularly useful for the fabrications of fuel elements for nutronic reactors.
Date:
June 25, 1959
Creator:
Lyon, W. L.
Object Type:
Report
System:
The UNT Digital Library
A Test of the Refraction Seismic Method on the Hanford Project
Information was desired on applicability of seismic methods of geophysical exploration in helping to better define and refine hydrological and geological factors affecting ground disposal of liquid radioactive wastes. To date most of information on the area geology has been obtained from surface mapping and well drilling, although it has long been recognized that geophysical techniques may greatly assist in defining the geology of the region. Although direct measurements are generally preferred to indirect measurements have proven extremely valuable in many applications. Careful analysis of field data from geophysical measurements, and correlation with known geologic conditions, should provide significant knowledge of earth formations. Geophysical methods do not directly determine depth, type and composition of underground earth materials, but rely rather on detecting differences in physical properties (elastic wave velocity, magnetic susceptibility, density or electrical resistivity) of such earth materials.
Date:
September 25, 1959
Creator:
Raymond, J. R.
Object Type:
Report
System:
The UNT Digital Library
Neutron Streaming Through Boundaries in a Mock-Up of the SIR Rotating Plug
This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank source strength and dimensions did not permit the tests to be extended to the full plug height. In view of the concern aroused by the ORNL tests and the absence of fundamental information on the transmission of neutrons through steel and the addition height (12') available here resulted in a request for BNL to construct and test a mock-up of a sector of the SIR top plug in accordance with KAPL specifications.
Date:
March 25, 1953
Creator:
Kouts, Herbert, J. C.; Pratt, William, W.; Schamberger, Robert, D.; Shore, Ferdinand, J.; Sleeper, Harvey, P., Jr. & Susskind, Herbert
Object Type:
Report
System:
The UNT Digital Library
Stored Energy in BNL Reactor Graphite
Radiation damage to graphite has several consequences of practical importance. The growth of graphite under radiation (Wigner's disease) in production reactors has always been a serious concern. The thermal conductivity of graphite decreases greatly with time of irradiation and is important in long range studies of reactor temperature problems.
Date:
February 25, 1953
Creator:
Chernick, J.
Object Type:
Report
System:
The UNT Digital Library
Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles
In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations would be helpful in the design and selection of equipment. Some progress has been made toward gaining a greater knowledge of the bundle characteristics under low temperature conditions. This report includes the development of relationship for the effect of temperature on pressure drop.
Date:
January 25, 1960
Creator:
Gartin, W. J.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.
The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (loop decontamination factors).
Date:
November 25, 1959
Creator:
Weed, R. D.
Object Type:
Report
System:
The UNT Digital Library
Oxygen Removal with Hydrazine- Interim Report
During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that filtered water will be used for this purpose. Since filtered water contains substantial amounts of dissolved solids (approximately 100 parts per million), and since it is saturated with air, this type of operation will have to be investigated with regard to corrosion problems. A particularly serious problem will be present after the system has been decontaminated, since the high temperature oxide films will have been removed and the bars metal surfaces will be exposed to the coolant.
Date:
January 25, 1960
Creator:
Demmitt, Thomas F.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Report on pH Control by Ion Exchange in High pH Systems
The primary purpose of a cleanup system in a recirculating water loop is to maintain the best possible water quality conditions. This is normally accomplished by continuously purifying all or a portion of the coolant. A secondary objective of the cleanup system is to help maintain the system pH at a constant value. A system that will satisfactorily accomplish both of these objectives is at times difficult to obtain. Generally the pH control characteristics are sacrificed in favor of the more important cleanup requirements. A somewhat new approach to the problem pf cleanup system design appears to offer a solution to this problem for high pH systems.
Date:
April 25, 1960
Creator:
Demmitt, Thomas F.
Object Type:
Report
System:
The UNT Digital Library
Pb-Sn Alloy Replacements for UO2 Density Standards
A correlation between the optical densities if the Pb-Sn alloy system and UO2 with respect to Co^60 gamma radiation has been determined. This enables one to fabricate density standards of whatever geometry may be desired for one in the gamma absorptiometer by simply casting a Pb-Sn alloy of the proper composition to correspond to the density required.
Date:
April 25, 1960
Creator:
Christensen, J. A.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I.
This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date:
November 25, 1955
Creator:
Williams, D. V. P.
Object Type:
Report
System:
The UNT Digital Library
A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid
Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be 6¢ per pound of HF.
Date:
May 25, 1956
Creator:
Marinsky, J. A. & Giuffrida, A. J.
Object Type:
Report
System:
The UNT Digital Library
Texas Register, Volume 47, Number 12, Pages 1541-1650, March 25, 2022
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date:
March 25, 2022
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Register, Volume 47, Number 8, Pages 821-1020, February 25, 2022
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date:
February 25, 2022
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
The Chemistry of Vanadium: A Summary of the Non-Project Literature Through November, 1952
The non-project literature concerning the chemistry of vanadium has been summarized through November, 1952. The report is presented in terms of izo- and heteropoly vanadates and cationic forms of pentavalent vanadium, complexes of di-, tri-, and pentavalent vanadium, and oxidation potentials of various vanadium systems. A bibliography of 93 references is included.
Date:
June 25, 1954
Creator:
Frank, Andrew J.
Object Type:
Report
System:
The UNT Digital Library
The Determination of Fission Product Gamma Doses
In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.
Date:
February 25, 1957
Creator:
Ruehle, William G.
Object Type:
Report
System:
The UNT Digital Library