Advanced Neutron Source Enrichment Study

Download Advanced Neutron Source Enrichment Study full books in PDF, epub, and Kindle. Read online Advanced Neutron Source Enrichment Study ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!

Advanced Neutron Source Enrichment Study. Volume 2

Author :
Publisher :
ISBN 13 :
Total Pages : 592 pages
Book Rating : 4.:/5 (16 download)

DOWNLOAD NOW!

Book Synopsis Advanced Neutron Source Enrichment Study. Volume 2 by :

Download or read book Advanced Neutron Source Enrichment Study. Volume 2 written by and published by . This book was released on 1994 with total page 592 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study has been performed of the impact on performance of using low enriched uranium (20% 235U) or medium enriched uranium (35% 235U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology. Volume 2 of this report contains 26 appendices containing results, meeting minutes, and fuel panel presentations. There are 26 appendices in this volume.

Mason Bishop Family Collection

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (679 download)

DOWNLOAD NOW!

Book Synopsis Mason Bishop Family Collection by :

Download or read book Mason Bishop Family Collection written by and published by . This book was released on 1888 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Collection consists of miscellaneous programs from Kalamazoo and Battle Creek, Michigan, musical societies, 1909-1945; four yearbooks of the Daughters of the American Revolution, Kalamazoo Chapter, 1952-1956; one Wedding Costumes booklet, published by Doubleday Brothers and Co.; one WMU Women's League Handbook, 1928-1929; Calendar of the Circuit Court and petit jurors list, Kalamazoo County, April term, 1949; Bishop family correspondence, 1909-1913; Michigan Federation [of Women's Clubs] cookbook, 1909; Prairie Farmer Union certificate, 1941; Bird's Eye View map of Vicksburg, Michigan, 1880; various theatrical, concert, and graduation programs, 1909-1905; a notebook, a certificate, a souvenir, a receipt and return envelopes, a ballot, and a prescription.

Advanced Neutron Source Enrichment Study

Author :
Publisher :
ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (683 download)

DOWNLOAD NOW!

Book Synopsis Advanced Neutron Source Enrichment Study by :

Download or read book Advanced Neutron Source Enrichment Study written by and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study has been performed of the impact on performance of using low enriched uranium (20% 235U) or medium enriched uranium (35% 235U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology.

Fuel Density, Uranium Enrichment, and Performance Studies for the Advanced Neutron Source Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.:/5 (685 download)

DOWNLOAD NOW!

Book Synopsis Fuel Density, Uranium Enrichment, and Performance Studies for the Advanced Neutron Source Reactor by :

Download or read book Fuel Density, Uranium Enrichment, and Performance Studies for the Advanced Neutron Source Reactor written by and published by . This book was released on 1994 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: Consistent with the words of the budget request for the Advanced Neutron Source (ANS), DOE commissioned a study of the impact on performance of using medium- or low-enriched uranium (MEU or LEU) in the fuel of the reactor that generates the neutrons. In the course of the study, performance calculations for 19 different combinations of reactor core volume, fuel density and enrichment, power level, and other relevant parameters were carried out. Since then, another 14 cases have been analyzed at Oak Ridge to explore some of the more interesting and important configurations and to gain further insights into the tradeoffs between performance and enrichment. Furthermore, with the aid of the data from these additional cases, we have been able to correlate the most important performance parameters (peak thermal neutron flux in the reflector and core life) with reactor power, fuel density, and fuel enrichment. This enables us to investigate intermediate cases, or alternative cases that might be proposed by people within or outside the project, without the time and expense of doing completely new neutronics calculations for each new example. The main drivers of construction and operating costs are the reactor power level and the number of fuel plates to be fabricated each year; these quantities can be calculated from the correlations. The results show that the baseline two-element core design cannot be adapted to any practical fuel of greatly reduced enrichment without great performance penalties, but that a modification of the design, in which one additional fuel element is incorporated to provide extra volume for lower enrichment fuels, has the capability of using existing, or more advanced, fuel types to lower the uranium enrichment.

Studies of the Impact of Fuel Enrichment on the Performance of the Advanced Neutron Source Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : 9 pages
Book Rating : 4.:/5 (685 download)

DOWNLOAD NOW!

Book Synopsis Studies of the Impact of Fuel Enrichment on the Performance of the Advanced Neutron Source Reactor by :

Download or read book Studies of the Impact of Fuel Enrichment on the Performance of the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of a larger study involving several organizations, the Advanced Neutron Source (ANS) Project made performance calculations for 19 different combinations of reactor core volume, fuel density and enrichment, power level, and other relevant parameters. These calculations were performed by Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL). Subsequently, ORNL analyzed 14 other cases. With the aid of data from these 33 cases, the laboratory has been able to correlate the most important performance characteristics (peak thermal flux in the reflector and core life) with fuel enrichment, fuel density, and power. The correlations permits the investigation of additional cases without going to the expense of doing completely new neutronics calculations for each new one and can be used to prepare curves showing the effects of different enrichments and of different fuel densities within the entire range from existing technology to the very advanced, as yet undeveloped fuels that have been proposed from time to time.

Optimizing a Three-element Core Design for the Advanced Neutron Source Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (683 download)

DOWNLOAD NOW!

Book Synopsis Optimizing a Three-element Core Design for the Advanced Neutron Source Reactor by :

Download or read book Optimizing a Three-element Core Design for the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Source of neutrons in the proposed Advanced Neutron Source facility is a multipurpose research reactor providing 5-10 times the flux, for neutron beams, of the best existing facilities. Baseline design for the reactor core, based on the ''no new inventions'' rule, was an assembly of two annular fuel elements similar to those used in the Oak Ridge and Grenoble high flux reactors, containing highly enriched U silicide particles. DOE commissioned a study of the use of medium- or low-enriched U; a three-element core design was studied as a means to provide extra volume to accommodate the additional U compound required when the fissionable 235U has to be diluted with 238U to reduce the enrichment. This paper describes the design and optimization of that three-element core.

Relative Performance Properties of the ORNL Advanced Neutron Source Reactor with Reduced Enrichment Fuels

Author :
Publisher :
ISBN 13 :
Total Pages : 18 pages
Book Rating : 4.:/5 (685 download)

DOWNLOAD NOW!

Book Synopsis Relative Performance Properties of the ORNL Advanced Neutron Source Reactor with Reduced Enrichment Fuels by :

Download or read book Relative Performance Properties of the ORNL Advanced Neutron Source Reactor with Reduced Enrichment Fuels written by and published by . This book was released on 1994 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Three cores for the Advanced Neutron Source reactor, differing in size, enrichment, and uranium density in the fuel meat, have been analyzed. Performance properties of the reduced enrichment cores are compared with those of the HEU reference configuration. Core lifetime estimates suggest that none of these configurations will operate for the design goal of 17 days at 330 MW. With modes increases in fuel density and/or enrichment, however, the operating lifetimes of the HEU and MEU designs can be extended to the desired length. Achieving this lifetime with LEU fuel in any of the three studies cores, however, will require the successful development of denser fuels and/or structural materials with thermal neutron absorption cross sections substantially less than that of Al-6061. Relative to the HEU reference case, the peak thermal neutron flux in cores with reduced enrichment will be diminished by about 25--30%.

Conceptual Design Summary

Author :
Publisher :
ISBN 13 :
Total Pages : 157 pages
Book Rating : 4.:/5 (727 download)

DOWNLOAD NOW!

Book Synopsis Conceptual Design Summary by :

Download or read book Conceptual Design Summary written by and published by . This book was released on 1992 with total page 157 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is a new basic and applied research facility based on a powerful steady-state research reactor that provides beams of neutrons for measurements and experiments in the fields of materials science and engineering, biology, chemistry, materials analysis, and nuclear science. The useful neutron flux for these experiments will be at least five times, and in some cases twenty times, more than is available at the world's best existing facilities. In addition, ANS will provide irradiation capabilities for the production of radioisotopes for medical applications, research, and industry and facilities for materials irradiation testing. The need for a new steady-state neutron research facility in the United States was emphasized by the 1984 National Academy Report and confirmed by the Department of Energy's (DOE's) Energy Research Advisory Board in 1985. These studies defined a minimum thermal neutron flux requirement of 5 x 1019 m−2 · s−1. The National Steering Committee for an Advanced Neutron Source, with representation from the major fields of science that will use the facility, was established in 1986 and has continued to define the performance requirements and instrument layouts needed by the user community. To minimize technical risks and safety issues, the project adopted a policy of not relying upon new inventions to meet the minimum performance criteria, and the design presented in this report is built on technologies already used in other facilities and development programs: for example, the involute aluminum-clad fuel plates common to HFIR and ILL and the uranium silicide fuel developed in DOE's Reduced Enrichment for Research and Test Reactors program and tested in reactors worldwide. At the same time, every state-of-the-art technique has been implemented to optimize neutron beam delivery at the experiments.

Advanced Neutron Source Reactor Conceptual Safety Analysis Report, Three-element-core Design

Author :
Publisher :
ISBN 13 :
Total Pages : 56 pages
Book Rating : 4.:/5 (684 download)

DOWNLOAD NOW!

Book Synopsis Advanced Neutron Source Reactor Conceptual Safety Analysis Report, Three-element-core Design by :

Download or read book Advanced Neutron Source Reactor Conceptual Safety Analysis Report, Three-element-core Design written by and published by . This book was released on 1996 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron Source has been proposed. The proposed core configuration consists of inner, middle, and outer elements, with the middle element offset axially beneath the inner and outer elements, which are axially aligned. The three-element-core RELAP5 model assumes that the reactor hardware is changed only within the core region, so that the loop piping, heat exchangers, and pumps remain as assumed for the two-element-core configuration. To assess the impact of changes in the core region configuration and the thermal-hydraulic steady-state conditions, the safety analysis has been updated. This report gives the safety margins for the loss-of-off-site power and pressure-boundary fault accidents based on the RELAP5 results. AU margins are greater for the three-element-core simulations than those calculated for the two-element core.

The Advanced Neutron Source--designing to Meet the Needs of the User Community

Author :
Publisher :
ISBN 13 :
Total Pages : 9 pages
Book Rating : 4.:/5 (727 download)

DOWNLOAD NOW!

Book Synopsis The Advanced Neutron Source--designing to Meet the Needs of the User Community by :

Download or read book The Advanced Neutron Source--designing to Meet the Needs of the User Community written by and published by . This book was released on 1989 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is to be a multi-purpose neutron research center, constructed around a high-flux reactor now being designed at the Oak Ridge National Laboratory (ORNL). Its primary purpose is to place the United States in the forefront of neutron scattering in the twenty-first century. Other research programs include nuclear and fundamental physics, isotopes production, materials irradiation, and analytical chemistry. The Advanced Neutron Source will be a unique and invaluable research tool because of the unprecedented neutron flux available from the high intensity research reactor. But that reactor would be ineffective without world-class research facilities that allow the fullest utilization of the available neutrons. And, in turn, those research facilities will not produce new and exciting science without a broad population of users coming from all parts of the nation, and the world, placed in a simulating environment in which experiments can be effectively conducted, and in which scientific exchange is encouraged. This paper discusses the measures being taken to ensure that the design of the ANS focuses not only on the reactor, but on providing the experiment and user support facilities needed to allow its effective use. 5 refs., 4 figs.

Advanced Neutron Source Reactor Thermal Analysis of Fuel Plate Defects

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (683 download)

DOWNLOAD NOW!

Book Synopsis Advanced Neutron Source Reactor Thermal Analysis of Fuel Plate Defects by :

Download or read book Advanced Neutron Source Reactor Thermal Analysis of Fuel Plate Defects written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source Reactor (ANSR) is a research reactor designed to provide the highest continuous neutron beam intensity of any reactor in the world. The present technology for determining safe operations were developed for the High Flux Isotope Reactor (HFIR). These techniques are conservative and provide confidence in the safe operation of HFIR. However, the more intense requirements of ANSR necessitate the development of more accurate, but still conservative, techniques. This report details the development of a Local Analysis Technique (LAT) that provides an appropriate approach. Application of the LAT to two ANSR core designs are presented. New theories of the thermal and nuclear behavior of the U[sub 3]Si[sub 2] fuel are utilized. The implications of lower fuel enrichment and of modifying the inspection procedures are also discussed. Development of the computer codes that enable the automate execution of the LAT is included.

The Advanced Neutron Source Research and Development Plan

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (683 download)

DOWNLOAD NOW!

Book Synopsis The Advanced Neutron Source Research and Development Plan by :

Download or read book The Advanced Neutron Source Research and Development Plan written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is being designed as a user-oriented neutron research laboratory centered around the most intense continuous beams of thermal and subthermal neutrons in the world (an order of magnitude more intense than beams available from the most advanced existing reactors). The ANS will be built around a new research reactor of 330-MW fission power, producing an unprecedented peak thermal flux of>7[center-dot] 10[sup 19][center-dot] m[sup -2][center-dot] s[sup -1]. Primarily a research facility, the ANS will accommodate more than 1000 academic, industrial, and government researchers each year. They will conduct basic research in all branches of science as well as applied research leading to better understanding of new materials, including high temperature super conductors, plastics, and thin films. Some 48 neutron beam stations will be set up in the ANS beam rooms and the neutron guide hall for neutron scattering and for fundamental and nuclear physics research. There also will be extensive facilities for materials irradiation, isotope production, and analytical chemistry. The top level work breakdown structure (WBS) for the project. As noted in this figure, one component of the project is a research and development (R & D) program (WBS 1.1). This program interfaces with all of the other project level two WBS activities. Because one of the project guidelines is to meet minimum performance goals without relying on new inventions, this R & D activity is not intended to produce new concepts to allow the project to meet minimum performance goals. Instead, the R & D program will focus on the four objectives described.

The Advanced Neutron Source

Author :
Publisher :
ISBN 13 :
Total Pages : 19 pages
Book Rating : 4.:/5 (727 download)

DOWNLOAD NOW!

Book Synopsis The Advanced Neutron Source by :

Download or read book The Advanced Neutron Source written by and published by . This book was released on 1993 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses the following on the Advanced Neutron Source: A global view; neutron research improves our lives; the challenge; the solution; neutron research; some major applications; environmental, safety, and health considerations; education; what the ANS means for local communities; and what will the ANS cost.

Advanced Neutron Source

Author :
Publisher :
ISBN 13 :
Total Pages : 4 pages
Book Rating : 4.:/5 (727 download)

DOWNLOAD NOW!

Book Synopsis Advanced Neutron Source by :

Download or read book Advanced Neutron Source written by and published by . This book was released on 1990 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is a research facility based on a 350 MW beam reactor, to be brought into service at the Oak Ridge National Laboratory at the end of the century. The primary objective is to provide high-flux neutron beams and guides, with cold, thermal, hot, and ultra-cold neutrons, for research in many fields of science. Secondary objectives include isotopes production, materials irradiation and activation analysis. The design of the ANS is strongly influenced by the historical development of research and power reactor concepts, and of the regulatory infrastructure of the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). Current trends in reactor safety also impact the climate for the design of such a reactor.

Energy Research Abstracts

Author :
Publisher :
ISBN 13 :
Total Pages : 782 pages
Book Rating : 4.3/5 (129 download)

DOWNLOAD NOW!

Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Assessment of Laser-Driven Pulsed Neutron Sources for Poolside Neutron-based Advanced NDE - A Pathway to LANSCE-like Characterization at INL.

Download Assessment of Laser-Driven Pulsed Neutron Sources for Poolside Neutron-based Advanced NDE - A Pathway to LANSCE-like Characterization at INL. PDF Online Free

Author :
Publisher :
ISBN 13 :
Total Pages : 64 pages
Book Rating : 4.:/5 (985 download)

DOWNLOAD NOW!

Book Synopsis Assessment of Laser-Driven Pulsed Neutron Sources for Poolside Neutron-based Advanced NDE - A Pathway to LANSCE-like Characterization at INL. by :

Download or read book Assessment of Laser-Driven Pulsed Neutron Sources for Poolside Neutron-based Advanced NDE - A Pathway to LANSCE-like Characterization at INL. written by and published by . This book was released on 2017 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt: A variety of opportunities for characterization of fresh nuclear fuels using thermal (~25meV) and epithermal (~10eV) neutrons have been documented at Los Alamos National Laboratory. They include spatially resolved non-destructive characterization of features, isotopic enrichment, chemical heterogeneity and stoichiometry. The LANSCE spallation neutron source is well suited in neutron fluence and temporal characteristics for studies of fuels. However, recent advances in high power short pulse lasers suggest that compact neutron sources might, over the next decade, become viable at a price point that would permit their consideration for poolside characterization on site at irradiation facilities. In a laser-driven neutron source the laser is used to accelerate deuterium ions into a beryllium target where neutrons are produced. At this time, the technology is new and their total neutron production is approximately four orders of magnitude less than a facility like LANSCE. However, recent measurements on a sub-optimized system demonstrated>1010 neutrons in sub-nanosecond pulses in predominantly forward direction. The compactness of the target system compared to a spallation target may allow exchanging the target during a measurement to e.g. characterize a highly radioactive sample with thermal, epithermal, and fast neutrons as well as hard X-rays, thus avoiding sample handling. At this time several groups are working on laser-driven neutron production and are advancing concepts for lasers, laser targets, and optimized neutron target/moderator systems. Advances in performance sufficient to enable poolside fuels characterization with LANSCE-like fluence on sample within a decade may be possible. This report describes the underlying physics and state-of-the-art of the laser-driven neutron production process from the perspective of the DOE/NE mission. It also discusses the development and understanding that will be necessary to provide customized capability for characterization of irradiated fuels. Potential operational advantages compared to a spallation neutron source include reduced shielding complexity, reduced energy requirements, and a production target free of fission products. Contributors to this report include experts in laser-driven neutron production (Roth, Fernandez), laser design (Haefner, Siders, Leemans), laser target design (Glenzer), spallation target/moderator design (Mocko), neutron instrumentation and characterization applications (Vogel, Bourke).

Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors

Author : National Academies of Sciences, Engineering, and Medicine
Publisher : National Academies Press
ISBN 13 : 0309379210
Total Pages : 205 pages
Book Rating : 4.3/5 (93 download)

DOWNLOAD NOW!

Book Synopsis Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors by : National Academies of Sciences, Engineering, and Medicine

Download or read book Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors written by National Academies of Sciences, Engineering, and Medicine and published by National Academies Press. This book was released on 2016-02-12 with total page 205 pages. Available in PDF, EPUB and Kindle. Book excerpt: The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.