Gallium In Nuclear Reactors
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Author | : Robert Isaac Jaffee |
Publisher | : |
Total Pages | : 40 |
Release | : 1952 |
Genre | : Corrosion resistant alloys |
ISBN | : |
The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. Thus, one desires a coolant which possess a low cross section for absorbing neutrons, good heat-transfer efficiency, a low melting point and a high boiling point. The element gallium possesses some of the requisite properties. It is a unique material, having a very low melting point, and a very high boiling point. Being a liquid metal, the heat transfer characteristics would be good, though not so good as those of some other liquid metals. The absorption cross section of gallium is rather high, which is a severe handicap. Since the cross section might be reduced by proper alloying, and since good coolants need be present in the reactor in only relatively small amounts, one cannot rule out the use of gallium on account of its cross section alone. Since gallium had some promise as a reactor coolant, research on the subject was merited.
Author | : |
Publisher | : |
Total Pages | : 39 |
Release | : 1949 |
Genre | : |
ISBN | : |
The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. Thus, one desires a coolant which possess a low cross section for absorbing neutrons, good heat-transfer efficiency, a low melting point and a high boiling point. The element gallium possesses some of the requisite properties. It is a unique material, having a very low melting point, and a very high boiling point. Being a liquid metal, the heat transfer characteristics would be good, though not so good as those of some other liquid metals. The absorption cross section of gallium is rather high, which is a severe handicap. Since the cross section might be reduced by proper alloying, and since good coolants need be present in the reactor in only relatively small amounts, one cannot rule out the use of gallium on account of its cross section alone. Since gallium had some promise as a reactor coolant, research on the subject was merited.
Author | : A. Kh Breger |
Publisher | : |
Total Pages | : 16 |
Release | : 1960 |
Genre | : Gallium alloys |
ISBN | : |
The alloy in In-Ga is activated by the leakage neutrons in the activity generator which is a horizontal container, which overlaps one of the sides of the reactor, and which gives off gamma radiation energy in the irradiator located in the cell; this cell is shielded from the neutron radiation of the reactor. The circulation of the alloy in the system 'activity generator-irradiator' is assured by an electromagnetic pump which, as we know, does not disturb the air-tightness of the system. The indium-gallium eutectic alloy in our case is the most suitable gamma carrier.
Author | : S. K. Haynes |
Publisher | : |
Total Pages | : 6 |
Release | : 1947 |
Genre | : Evaporation |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 33 |
Release | : 1997 |
Genre | : |
ISBN | : |
The disposition of plutonium from decommissioned nuclear weapons, by incorporation into commercial UO2-based nuclear reactor fuel, is a viable means to reduce the potential for theft of excess plutonium. This fuel, which would be a combination of plutonium oxide and uranium oxide, is referred to as a mixed oxide (MOX). Following power generation in commercial reactors with this fuel, the remaining plutonium would become mixed with highly radioactive fission products in a spent fuel assembly. The radioactivity, complex chemical composition, and large size of this spent fuel assembly, would make theft difficult with elaborate chemical processing required for plutonium recovery. In fabricating the MOX fuel, it is important to maintain current commercial fuel purity specifications. While impurities from the weapons plutonium may or may not have a detrimental affect on the fuel fabrication or fuel/cladding performance, certifying the effect as insignificant could be more costly than purification. Two primary concerns have been raised with regard to the gallium impurity: (1) gallium vaporization during fuel sintering may adversely affect the MOX fuel fabrication process, and (2) gallium vaporization during reactor operation may adversely affect the fuel cladding performance. Consequently, processes for the separation of plutonium from gallium are currently being developed and/or designed. In particular, two separation processes are being considered: (1) a developmental, potentially lower cost and lower waste, thermal vaporization process following PuO2 powder preparation, and (2) an off-the-shelf, potentially higher cost and higher waste, aqueous-based ion exchange (IX) process. While it is planned to use the thermal vaporization process should its development prove successful, IX has been recommended as a backup process. This report presents a preconceptual design with material balances for separation of plutonium from gallium by IX.
Author | : A. Kh Breger |
Publisher | : |
Total Pages | : 15 |
Release | : 1963 |
Genre | : |
ISBN | : |
The alloy in In-Ga is activated by the leakage neutrons in the activity generator which is a horizontal container, which overlaps one of the sides of the reactor, and which gives off gamma radiation energy in the irradiator located in the cell; this cell is shielded from the neutron radiation of the reactor. The circulation of the alloy in the system 'activity generator-irradiator' is assured by an electromagnetic pump which, as we know, does not disturb the air-tightness of the system. The indium-gallium eutectic alloy in our case is the most suitable gamma carrier.
Author | : Vernon James Ehlers |
Publisher | : |
Total Pages | : 122 |
Release | : 1960 |
Genre | : Gallium |
ISBN | : |
Author | : Gerald Johnston |
Publisher | : Springer Science & Business Media |
Total Pages | : 267 |
Release | : 2012-12-06 |
Genre | : Medical |
ISBN | : 1461344964 |
In 1970, under the sponsorship of Oak Ridge Associated Univer sities (ORAU), a group of clinical investigators formed the Cooper ative Group to Study Localization of Radiopharmaceuticals. The first radiopharmaceutical selected for study was 67-Gallium (67-Ga) administered as the citrate. The object of the study was to de termine the usefulness of 67-Ga in the diagnosis and treatment of patients with various malignancies. Funding for the project was granted by the U. S. Atomic Energy Commission and the National Cancer Institute, National Institutes of Health (NIH). The Nuclear Medicine Department of the Clinical Center, NIH, agreed to assist ORAU with aspects of this study, particularly with 67-Ga scin tigraphy of patients with lymphoma and Hodgkin's disease. Pre liminary reports from the ORAU study are in press. Since April 1971, 67-Ga scintigraphy has gained increasing use in the study of cancer patients at the Clinical Center, NIH, where well over 1000 such patients have been examined by this method. This monograph was written to present selected examples from this group of a variety of malignancies seen in this 28-month period. No attempt has been made to correlate this overall experience statistically. Rather, this presentation is to help familiarize the practitioner of Nuclear Medicine with the wide range of usefulness for 67-Ga scintigraphy while making him aware of the variation in scan appearance and watchful of the many pitfalls of 67-Ga scan interpretation. Permission to use these patient studies and x-rays was generously granted by Dr. Paul P.
Author | : James M. Essig |
Publisher | : CreateSpace |
Total Pages | : 68 |
Release | : 2015-06-17 |
Genre | : |
ISBN | : 9781514396339 |
Totally covalently bonded Gallium-69 as a concept is nothing particularly new and is not of my origination. However, due to the small amount of available literature on the subject, I thought that my prosaic approach to the concept with additional concepts would be illustrative of the great potential of chemical energy. Chemical energy in degenerate matter forms especially in totally covalently bonded heavy elements may enable explosive yields mid-way between the highest performing contemporary chemical fuels and nuclear fissile fuels. Thus, the concepts presented herein need further study for potential technological applications. In cases where the potential chemical energy would match or surpass the nuclear fissile energy of fissile fuels, exotically powerful explosive devices are plausible which can have military and peaceful applications. One application that stands out is compact and extreme invariant mass-specific energy density fuels for powering spacecraft such as relativistic rockets and pellet runway power spacecraft.
Author | : |
Publisher | : |
Total Pages | : 10 |
Release | : 1997 |
Genre | : |
ISBN | : |
Gallium present in weapons plutonium must be removed before it can be used for the production of mixed-oxide (MOX) nuclear reactor fuel. The main goal of the preliminary studies conducted at Texas A and M University was to assist in the development of a thermal process to remove gallium from a gallium oxide/plutonium oxide matrix. This effort is being conducted in close consultation with the Los Alamos National Laboratory (LANL) personnel involved in the development of this process for the US Department of Energy (DOE). Simple experiments were performed on gallium oxide, and cerium-oxide/gallium-oxide mixtures, heated to temperatures ranging from 700--900 C in a reducing environment, and a method for collecting the gallium vapors under these conditions was demonstrated.