Thermal-hydraulic Studies of the Advanced Neutron Source Cold Source

Thermal-hydraulic Studies of the Advanced Neutron Source Cold Source

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Published: 1995

Total Pages: 37

ISBN-13:

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The Advanced Neutron Source (ANS), in its conceptual design phase at Oak Ridge National Laboratory, was to be a user-oriented neutron research facility producing the most intense steady-state flux of thermal and cold neutrons in the world. Among its many scientific applications, the production of cold neutrons was a significant research mission for the ANS. The cold neutrons come from two independent cold sources positioned near the reactor core. Contained by an aluminum alloy vessel, each cold source is a 410-mm-diam sphere of liquid deuterium that functions both as a neutron moderator and a cryogenic coolant. With nuclear heating of the containment vessel and internal baffling, steady-state operation requires close control of the liquid deuterium flow near the vessel's inner surface. Preliminary thermal-hydraulic analyses supporting the cold source design were performed with heat conduction simulations of the vessel walls and multidimensional computational fluid dynamics simulations of the liquid deuterium flow and heat transfer. This report presents the starting phase of a challenging program and describes the cold source conceptual design, the thermal-hydraulic feasibility studies of the containment vessel, and the future computational and experimental studies that were planned to verify the final design.


Update to Advanced Neutron Source Steady-state Thermal-hydraulic Report

Update to Advanced Neutron Source Steady-state Thermal-hydraulic Report

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Published: 1996

Total Pages: 109

ISBN-13:

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This report is intended to be a supplement to ORNL/TM-12398, Steady-State Thermal-Hydraulic Design Analysis of the Advanced Neutron Source Reactor. It updates the core thermal-hydrualic design to the latest three-element configuration and also provides the most recent information on the thermal-hydraulic statistical uncertainty analysis. In addition, it includes calculations of beam tube cooling and control rod lift forces, which were not addressed in the initial report. This report describes work that is a snapshot in time as it stood at the end of the project. The three-element core calculations include a description of changes made to the overall coolant system; however, most of the analysis is focused on fuel loading thermal-hydraulic calculations. This analysis uses updated uncertainty values and indicates that a two-dimensional fuel grading in the three-element core would still be necessary to meet the desired operating and safety criteria. Analysis of cooling in the reflector tank examines various cooling options for the reflector tank components. This work investigated multiple forced convection designs as well as natural convection cooling requirements. Lift forces on the inner control rods caused by the upward coolant flow were also examined. Initial control rod designs were such that a sheared control rod would tend to lift because of flow forces. Design changes were recommended that would eliminate this issue. They included geometry changes to the inner control rod cooling channels, changes to the orificing in the central hole region, and reduction of inner control rod coolant velocity.


Advanced Neutron Source (ANS) Project Progress Report, FY 1991

Advanced Neutron Source (ANS) Project Progress Report, FY 1991

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Published: 1992

Total Pages: 99

ISBN-13:

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This report discusses the following about the Advanced Neutron Source: Project Management; Research and Development; Fuel Development; Corrosion Loop Tests and Analyses; Thermal-Hydraulic Loop Tests; Reactor Control and Shutdown Concepts; Critical and Subcritical Experiments; Material Data, Structural Tests, and Analysis; Cold-Source Development; Beam Tube, Guide, and Instrument Development; Hot-Source Development; Neutron Transport and Shielding; I C Research and Development; Design; and Safety.


NIST Liquid Hydrogen Cold Source

NIST Liquid Hydrogen Cold Source

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Published: 2006

Total Pages: 72

ISBN-13:

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Nearly two-thirds of the experiments performed at the NIST Center for Neutron Research (NCNR) utilize cold neutrons with wavelengths greater than 4 Angstroms. This report documents the development of the liquid hydrogen cold neutron source in the NIST research reactor. The source was designed to optimize the flux of cold neutrons transported to the scattering instruments in the guide hall. It was also designed to be passively safe, and operate simply and reliably. All hydrogen system components are surrounded with monitored helium containments to ensure that there are at least two barriers between the hydrogen and the atmosphere. Monte Carlo simulations were used to calculate the cold source performance and estimate the nuclear heat load at full reactor power. Thermal-hydraulic tests in a full-scale mockup at NIST Boulder confirmed that a naturally circulating thermosiphon driven by the 2 meter height of the condenser could easily supply the moderator vessel with liquid hydrogen while removing over 2000 watts. The cryostat assembly was designed to withstand any high pressure generated in a credible accident. It was fabricated to rigorous quality assurance standards, resulting in over 10 years of leak-free operation.


Cold Neutron Sources: Practical Considerations and Modern Research

Cold Neutron Sources: Practical Considerations and Modern Research

Author: International Atomic Energy Agency

Publisher: International Atomic Energy Agency

Published: 2024-01-24

Total Pages: 0

ISBN-13: 9789201394231

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This Safety Report provides guidance, targeted towards States newly embarking upon a nuclear power plant programme, on the licensing process and associated procedures needed during for the construction, commissioning and operation stages of a nuclear power plant, so that the applicant complies with national regulations in line with the internationally recognized safety principles and requirements throughout these stages. The publication elaborates on the generic guidance provided in IAEA Safety Standards Series No. SSG-12, Licensing Process for Nuclear Installations, and gives supplementary practical guidance for nuclear power plants.