Advanced Neutron Source Enrichment Study. Volume 2: Appendices -- Final Report, Revision 12/94

Advanced Neutron Source Enrichment Study. Volume 2: Appendices -- Final Report, Revision 12/94

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Published: 2001

Total Pages:

ISBN-13:

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A study has been performed of the impact on performance of using low enriched uranium (20%[sup 235]U) or medium enriched uranium (35%[sup 235]U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93%[sup 235]U. 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

Mason Bishop Family Collection

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Publisher:

Published: 1888

Total Pages:

ISBN-13:

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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

Advanced Neutron Source Enrichment Study

Author:

Publisher:

Published: 1994

Total Pages: 8

ISBN-13:

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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.


The Advanced Neutron Source Research and Development Plan

The Advanced Neutron Source Research and Development Plan

Author:

Publisher:

Published: 1992

Total Pages: 147

ISBN-13:

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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. The ANS will be built around a new research reactor of [approximately] 330 MW fission power, producing an unprecedented peak thermal flux of> 7 [times] 10[sup 19] M[sup [minus]2] [center dot] S[sup [minus]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 R D program will focus on the four objectives: Address feasibility issues; provide analysis support; evaluate options for improvement in performance beyond minimum requirements; and provide prototype demonstrations for unique facilities. The remainder of this report presents (1) the process by which the R D activities are controlled and (2) a discussion of the individual tasks that have been identified for the R D program, including their justification, schedule and costs. The activities discussed in this report will be performed by Martin Marietta Energy Systems, Inc. (MMES) through the Oak Ridge National Laboratory (ORNL) and through subcontracts with industry, universities, and other national laboratories. It should be noted that in general a success path has been assumed for all tasks.


Neutron Generators for Analytical Purposes

Neutron Generators for Analytical Purposes

Author: International Atomic Energy Agency

Publisher: IAEA Radiation Technology Repo

Published: 2012

Total Pages: 145

ISBN-13: 9789201251107

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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.


The Advanced Neutron Source

The Advanced Neutron Source

Author:

Publisher:

Published: 1990

Total Pages: 7

ISBN-13:

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The Advanced Neutron Source (ANS) is a new user experimental facility planned to be operational at Oak Ridge in the late 1990's. The centerpiece of the ANS will be a steady-state research reactor of unprecedented thermal neutron flux ([phi]{sub th} ≈ 8 × 1019 m−2 {center dot}s−1) accompanied by extensive and comprehensive equipment and facilities for neutron-based research.