Advanced Neutron Source Final Preconceptual Reference Core Design
Advanced Neutron Source Final Preconceptual Reference Core Design

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Publisher:

Published: 1989

Total Pages:

ISBN-13:

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The preconceptual design phase of the Advanced Neutron Source (ANS) Project ended with the selection of a reference reactor core that will be used to begin conceptual design work. The new reference core consists of two involute fuel elements, of different diameters, aligned axially with a small axial gap between them. The use of different element diameters permits a separate flow of coolant to be provided for each one, thus enhancing the heat removal capability and increasing the thermal-hydraulic margins. The improved cooling allows the elements to be relatively long and thin, so self-shielding is reduced and an acceptable core life can be achieved with a relatively small loading of highly enriched uranium silicide fuel clad in aluminium. The new reference design has a fueled volume 67.4 L, each element having a heated length of 474 mm and a radial fuel thickness of 66 mm. The end-of-cycle peak thermal flux in the large heavy-water reflector tank around the core is estimated to be in the range of 0.8 to 1.0 /times/ 10/sup 20/ m/sup /minus/2/ /center dot/ s/sup /minus/1/. 7 refs., 23 figs., 15 tabs.

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

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Publisher:

Published: 1995

Total Pages: 8

ISBN-13:

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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.

Reactivity Studies on the Advanced Neutron Source. [Advanced Neutron Source].
Reactivity Studies on the Advanced Neutron Source. [Advanced Neutron Source].

Author:

Publisher:

Published: 1990

Total Pages: 8

ISBN-13:

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An Advanced Neutron Source (ANS) with a peak thermal neutron flux of about 8.5 x 1019 m−2s−1 is being designed for condensed matter physics, materials science, isotope production, and fundamental physics research. The ANS is a new reactor-based research facility being planned by Oak Ridge National Laboratory (ORNL) to meet the need for an intense steady-state source of neutrons. The design effort is currently in the conceptual phase. A reference reactor design has been selected in order to examine the safety, performance, and costs associated with this one design. The ANS Project has an established, documented safety philosophy, and safety-related design criteria are currently being established. The purpose of this paper is to present analyses of safety aspects of the reference reactor design that are related to core reactivity events. These analyses include control rod worth, shutdown rod worth, heavy water voiding, neutron beam tube flooding, light water ingress, and single fuel element criticality. Understanding these safety aspects will allow us to make design modifications that improve the reactor safety and achieve the safety related design criteria. 8 refs., 3 tabs.

Nuclear Reactor Technology Development and Utilization
Nuclear Reactor Technology Development and Utilization

Author: Salah Ud-Din Khan

Publisher: Woodhead Publishing

Published: 2020-06-16

Total Pages: 514

ISBN-13: 0128189436

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Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear setting. As countries across the globe realize their plans for a sustainable energy future, the need for innovative nuclear reactor design is increasing, and this book will provide a deep understanding of how these technologies can aid in a region’s goal for clean and reliable energy. Dr Khan and Dr Nakhabov, alongside their team of expert contributors, discuss a variety of important topics, including nuclear fuel cycles, plant decommissioning and hybrid energy systems, while considering a variety of diverse uses such as nuclear desalination, hydrogen generation and radioisotope production. Knowledge acquired enables the reader to conduct further research in academia and industry, and apply the latest design, development, integration, safety and economic guidance to their work and research. Combines reactor fundamentals with a contemporary look at evolving trends in the design of advanced reactors and their application to both nuclear and non-nuclear uses Analyses the latest research and uses of hybrid systems which bring together nuclear technology with renewable energy technologies Presents applications, economic factors and an analysis of sustainability factors in one comprehensive resource