Download or read book Advanced Neutron Source Reactor Zoning Shielding and Radiological Optimization Guide written by and published by . This book was released on 1995 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the design of major nuclear facilities, it is important to protect both humans and equipment excessive radiation dose. Past experience has shown that it is very effective to apply dose reduction principles early in the design of a nuclear facility both to specific design features and to the manner of operation of the facility, where they can aid in making the facility more efficient and cost-effective. Since the appropriate choice of radiological controls and practices varies according to the case, each area of the facility must be analyzed for its radiological impact, both by itself and in interactions with other areas. For the Advanced Neutron Source (ANS) project, a large relational database will be used to collect facility information by system and relate it to areas. The database will also hold the facility dose and shielding information as it is produced during the design process. This report details how the ANS zoning scheme was established and how the calculation of doses and shielding are to be done.
Download or read book Protection Against Neutron Radiation written by National Council on Radiation Protection and Measurements and published by . This book was released on 1971 with total page 168 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Shielding Design Manual written by Theodore Rockwell and published by . This book was released on 1956 with total page 496 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Advances in Radiation Shielding for Fusion Reactors written by Rafael Juarez Manas and published by Woodhead Publishing. This book was released on 2021-02-15 with total page 400 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances in Radiation Shielding for Fusion Reactors provides complete guidance on radiation shielding principles and their application to nuclear fusion facilities, incorporating the lessons learnt from the design and construction of the latest major modern nuclear fusion facilities such as ITER. It provides an insight of the main challenges and the computational approach to deal with them efficiently. Although applicable to general radiation shielding problems, specific attention is given to problems associated with conceptual fusion reactors. This includes neutron and gamma-ray shielding in deep penetration and streaming geometries, activation, radio-active waste, occupational radiation exposure and ALARA. Descriptions of shielding issues for fusion reactors, and shielding principles and strategies, and lessons learnt from the conception and construction of ITER Advanced and modern computation methods to predict and analyse radiation fields in 3D to identify shielding needs or validate shielding proposals Revision of the main sources of uncertainty to be considered in these calculations and a methodology to determine and apply safety factors to mitigate the impact of uncertainties
Download or read book Global Shielding Analysis for the Three element Core Advanced Neutron Source Reactor Under Normal Operating Conditions written by and published by . This book was released on 1995 with total page 103 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two-dimensional discrete ordinates radiation transport calculations were performed for a model of the three-element core Advanced Neutron Source reactor design under normal operating conditions. The core consists of two concentric upper elements and a lower element radially centered in the annulus between the upper elements. The initial radiation transport calculations were performed with the DORT two-dimensional discrete ordinates radiation transport code using the 39-neutron-group/44-gamma-ray-group ANSL-V cross-section library, an S6 quadrature, and a P1 Legendre polynomial expansion of the cross sections to determine the fission neutron source distribution in the core fuel elements. These calculations were limited to neutron groups only. The final radiation transport calculations, also performed with DORT using the 39-neutron-group/44-gamma-ray-group ANSL-V cross-section library, an S{sub l0} quadrature, and a P3 Legendre polynomial expansion of the cross sections, produced neutron and gamma-ray fluxes over the full extent of the geometry model. Responses (or activities) at various locations in the model were then obtained by folding the appropriate response functions with the fluxes at those locations. Some comparisons were made with VENTURE-calculated (diffusion theory) 20-group neutron fluxes that were summed into four broad groups. Tne results were in reasonably good agreement when the effects of photoneutrons were not included, thus verifying the physics model upon which the shielding model was based. Photoneutrons increased the fast-neutron flux levels deep within the D20 several orders of magnitude. Results are presented as tables of activity values for selected radial and axial traverses, plots of the radial and axial traverse data, and activity contours superimposed on the calculational geometry model.
Download or read book The Development of Radiation Shielding Standards in the American Nuclear Society written by American Nuclear Society. Standards Committee. Shielding Standards Subcommittee and published by . This book was released on 1975 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Advanced Neutron Source Radiological Design Criteria written by and published by . This book was released on 1995 with total page 141 pages. Available in PDF, EPUB and Kindle. Book excerpt: The operation of the proposed Advanced Neutron Source (ANS) facility will present a variety of radiological protection problems. Because it is desired to design and operate the ANS according to the applicable licensing standards of the Nuclear Regulatory Commission (NRC), it must be demonstrated that the ANS radiological design basis is consistent not only with state and Department of Energy (DOE) and other usual federal regulations, but also, so far as is practicable, with NRC regulations and with recommendations of such organizations as the Institute of Nuclear Power Operations (INPO) and the Electric Power Research Institute (EPRI). Also, the ANS radiological design basis is in general to be consistent with the recommendations of authoritative professional and scientific organizations, specifically the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). As regards radiological protection, the principal goals of DOE regulations and guidance are to keep occupational doses ALARA [as low as (is) reasonably achievable], given the current state of technology, costs, and operations requirements; to control and monitor contained and released radioactivity during normal operation to keep public doses and releases to the environment ALARA; and to limit doses to workers and the public during accident conditions. Meeting these general design objectives requires that principles of dose reduction and of radioactivity control by employed in the design, operation, modification, and decommissioning of the ANS. The purpose of this document is to provide basic radiological criteria for incorporating these principles into the design of the ANS. Operations, modification, and decommissioning will be covered only as they are affected by design.
Download or read book Initial Global 2 D Shielding Analysis for the Advanced Neutron Source Core and Reflector written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document describes the initial global 2-D shielding analyses for the Advanced Neutron Source (ANS) reactor, the D[sub 2]O reflector, the reflector vessel, and the first 200 mm of light water beyond the reflector vessel. Flux files generated here will later serve as source terms in subsequent shielding analyses. In addition to reporting fluxes and other data at key points of interest, a major objective of this report was to document how these analyses were performed, the phenomena that were included, and checks that were made to verify that these phenomena were properly modeled. In these shielding analyses, the fixed neutron source distribution in the core was based on the'lifetime-averaged' spatial power distribution. Secondary gamma production cross sections in the fuel were modified so as to account intrinsically for delayed fission gammas in the fuel as well as prompt fission gammas. In and near the fuel, this increased the low-energy gamma fluxes by 50 to 250%, but out near the reflector vessel, these same fluxes changed by only a few percent. Sensitivity studies with respect to mesh size were performed, and a new 2-D mesh distribution developed after some problems were discovered with respect to the use of numerous elongated mesh cells in the reflector. All of the shielding analyses were performed sing the ANSL-V 39n/44g coupled library with 25 thermal neutron groups in order to obtain a rigorous representation of the thermal neutron spectrum throughout the reflector. Because of upscatter in the heavy water, convergence was very slow. Ultimately, the fission cross section in the various materials had to be artificially modified in order to solve this fixed source problem as an eigenvalue problem and invoke the Vondy error-mode extrapolation technique which greatly accelerated convergence in the large 2-D RZ DORT analyses. While this was quite effective, 150 outer iterations (over energy) were still required.
Download or read book Radiation Shielding written by J. Kenneth Shultis and published by Prentice Hall. This book was released on 1996 with total page 568 pages. Available in PDF, EPUB and Kindle. Book excerpt: 3 Mile Island. Chernobyl. Nuclear meltdowns that can spell disaster for decades to come. For a number of professions including nuclear engineering, environmental engineering, radiology, and space physics, the most hazardous aspect of the job is the proper handling of radioactive material and the assessment of radiation doses. This book provides an understanding of the principles and techniques used in modern radiation shield design and analysis.
Download or read book Neutron Generators for Analytical Purposes written by International Atomic Energy Agency and published by IAEA Radiation Technology Repo. This book was released on 2012 with total page 145 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication addresses recent developments in neutron generator (NG) technology. It presents information on compact instruments with high neutron yield to be used for neutron activation analysis (NAA) and prompt gamma neutron activation analysis in combination with high count rate spectrometers. Traditional NGs have been shown to be effective for applications including borehole logging, homeland security, nuclear medicine and the on-line analysis of aluminium, coal and cement. Pulsed fast thermal neutron analysis, as well as tagged and timed neutron analysis, are additional techniques which can be applied using NG. Furthermore, NG can effectively be used for elemental analysis and is also effective for analysis of hidden materials by neutron radiography. Useful guidelines for developing NG based research laboratories are also provided in this publication.
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1996 with total page 740 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Download or read book INIS Atomindex written by and published by . This book was released on 1996 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiological Characterization of Shut Down Nuclear Reactors for Decommissioning Purposes written by International Atomic Energy Agency and published by . This book was released on 1998 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes and assesses radiological characterization as a precursor to decommissioning. It shows the influence of the radioactive inventory on the planning and strategies of decommissioning and also presents an extensive overview of characterization results on various reactors which have been or are being decommissioned.
Download or read book Radiation Protection and Safety in Medical Uses of Ionizing Radiation written by International Atomic Energy Agency and published by . This book was released on 2019-02-04 with total page 318 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide provides recommendations and guidance on fulfilling the requirements of IAEA Safety Standards Series No. GSR Part 3 for ensuring radiation protection and safety of radiation sources in medical uses of ionizing radiation with regard to patients, workers, carers and comforters, volunteers in biomedical research, and the public. It covers radiological procedures in diagnostic radiology (including dentistry), image guided interventional procedures, nuclear medicine, and radiotherapy. Recommendations and guidance are provided on applying a systematic approach to ensure that there is a balance between being able to utilize the benefits from medical uses of ionizing radiation and minimizing the risk of radiation effects to people.
Download or read book Storage of Spent Nuclear Fuel written by International Atomic Energy Agency and published by . This book was released on 2021-04-30 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-15 and provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facility and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods beyond the original design lifetime of the storage facility that have become necessary owing to delays in the development of disposal facilities and the reduction in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. Guidance is provided on all stages in the lifetime of a spent fuel storage facility, from planning through siting and design to operation and decommissioning. The revision was undertaken by amending, adding and/or deleting specific paragraphs addressing recommendations and findings from studying the accident at the Fukushima Daiichi nuclear power plant in Japan.
Download or read book Proceedings of the Eleventh Meeting of the International Collaboration on Advanced Neutron Sources ICANS XI Plenary session accelerator workshop target station workshop written by International Collaboration on Advanced Neutron Sources. Meeting and published by . This book was released on 1991 with total page 662 pages. Available in PDF, EPUB and Kindle. Book excerpt:
