Safety Analysis of Enriched Uranium Processing PDF Download
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Author: H. T. Williams
Publisher:
ISBN:
Category : Radiation
Languages : en
Pages : 204
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Book Description
Author: A. H. Chura
Publisher:
ISBN:
Category :
Languages : en
Pages : 199
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Book Description
Author: H. T. Williams
Publisher:
ISBN:
Category : Radiation
Languages : en
Pages : 204
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Book Description
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 40
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Author: Finis S. Patton
Publisher:
ISBN:
Category :
Languages : en
Pages : 300
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Book Description
Author: Allan S. Krass
Publisher: Routledge
ISBN: 100020054X
Category : Political Science
Languages : en
Pages : 325
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Book Description
Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.
Author: U.S. Atomic Energy Commission. Health and Safety Laboratory
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 268
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 19
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Author: Benjamin Rickman
Publisher:
ISBN:
Category :
Languages : en
Pages : 40
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Book Description
In accordance with the 1986 amendment concerning licenses for research and test reactors, the MU Research Reactor (MURR) is planning to convert from using High-Enriched Uranium (HEU) fuel to the use of Low-Enriched Uranium (LEU) fuel. Since the approval of a new LEU fuel that could meet the MURR's per- formance demands, the next phase of action for the fuel conversion process is to create a new Safety Analysis Report (SAR) with respect to the LEU fuel. A component of the SAR includes the Maximum Hypothetical Accident (MHA) and accidents that qualify under the class of Fuel Handling Accidents (FHA). In this work, the dose to occupational staat the MURR is calculated for the FHAs. The radionuclide inventory for the proposed LEU fuel was calculated using the ORIGEN2 point-depletion code linked to the MURR neutron spectrum. The MURR spectrum was generated from a Monte Carlo Neutron transPort (MCNP) simulation. The coupling of these codes create MONTEBURNS, a time-dependent burnup code. The release fraction from each FHA within this analysis was estab- lished by the methodology of the 2006 HEU SAR, which was accepted by the NRC. The actual dose methodology was not recorded in the HEU SAR, so a conservative path was chosen. In compliance to NUREG 1537, when new methodology is used in a HEU to LEU analysis, it is necessary to re-evaluate the HEU accident. The Total Eective Dose Equivalent (TEDE) values were calculated in addi- tion to the whole body dose and thyroid dose to operation personnel. The LEU FHA occupational TEDE dose was 349 mrem which is under the NRC regula- tory occupational dose limit of 5 rem TEDE, and under the LEU MHA limit of 403 mrem. The re-evaluated HEU FHA occupational TEDE dose was 235 mrem,which is above the HEU MHA TEDE dose of 132 mrem. Since the new method- ology produces a dose that is larger than the HEU MHA, we can safely assume that it is more conservative than the previous, unspecied dose.
Author: IAEA (Corporate Author)
Publisher:
ISBN:
Category :
Languages : en
Pages : 100
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Book Description
This Safety Guide supplements the Safety Requirements publication on Safety of Fuel Cycle Facilities and addresses all the stages in the life cycle of conversion facilities (CFs) and enrichment facilities (EFs), with emphasis placed on design and operation. It describes the actions, conditions and procedures for meeting safety requirements and deals specifically with the handling, processing and storage of depleted, natural and low enriched uranium. The publication is intended to be of use to designers, operating organizations and regulators for ensuring the safety of conversion and enrichment.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 675
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Book Description
At present, most 99Mo is produced in research, test, or isotope production reactors by irradiation of highly enriched uranium targets. To achieve the denser form of uranium needed for switching from high to low enriched uranium (LEU), targets in the form of a metal foil (~125-150 μm thick) are being developed. The LEU High Density Target Project successfully demonstrated several iterations of an LEU-fission-based Mo-99 technology that has the potential to provide the world's supply of Mo-99, should major producers choose to utilize the technology. Over 50 annular high density targets have been successfully tested, and the assembly and disassembly of targets have been improved and optimized. Two target front-end processes (acidic and electrochemical) have been scaled up and demonstrated to allow for the high-density target technology to mate up to the existing producer technology for target processing. In the event that a new target processing line is started, the chemical processing of the targets is greatly simplified. Extensive modeling and safety analysis has been conducted, and the target has been qualified to be inserted into the High Flux Isotope Reactor, which is considered above and beyond the requirements for the typical use of this target due to high fluence and irradiation duration.
