HFIR Cold Neutron Source Moderator Vessel Design Analysis

HFIR Cold Neutron Source Moderator Vessel Design Analysis PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

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Book Description
A cold neutron source capsule made of aluminum alloy is to be installed and located at the tip of one of the neutron beam tubes of the High Flux Isotope Reactor. Cold hydrogen liquid of temperature approximately 20 degree Kelvin and 15 bars pressure is designed to flow through the aluminum capsule that serves to chill and to moderate the incoming neutrons produced from the reactor core. The cold and low energy neutrons thus produced will be used as cold neutron sources for the diffraction experiments. The structural design calculation for the aluminum capsule is reported in this paper.

HFIR Cold Neutron Source Moderator Vessel Design Analysis

HFIR Cold Neutron Source Moderator Vessel Design Analysis PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

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Book Description
A cold neutron source capsule made of aluminum alloy is to be installed and located at the tip of one of the neutron beam tubes of the High Flux Isotope Reactor. Cold hydrogen liquid of temperature approximately 20 degree Kelvin and 15 bars pressure is designed to flow through the aluminum capsule that serves to chill and to moderate the incoming neutrons produced from the reactor core. The cold and low energy neutrons thus produced will be used as cold neutron sources for the diffraction experiments. The structural design calculation for the aluminum capsule is reported in this paper.

Cold Source Moderator Vessel Development for the High Flux Isotope Reactor

Cold Source Moderator Vessel Development for the High Flux Isotope Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

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Book Description
A project is underway at Oak Ridge National Laboratory (ORNL) to design, test, and install a cold neutron source facility in the High Flux Isotope Reactor (HFIR). This new cold source employs supercritical hydrogen at cryogenic temperatures both as the medium for neutron moderation and as the working fluid for removal of internally-generated nuclear heating. The competing design goals of minimizing moderator vessel mass and providing adequate structural integrity for the vessel motivated the requirement of detailed multidimensional thermal-hydraulic analyses of the moderator vessel as a critical design subtask. This paper provides a summary review of the HFIR cold source moderator vessel design and a description of the thermal-hydraulic studies that were carried out to support the vessel development.

The High Flux Isotope Reactor (HFIR) Cold Source Project at ORNL.

The High Flux Isotope Reactor (HFIR) Cold Source Project at ORNL. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 9

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Book Description
Following the decision to cancel the Advanced Neutron Source (ANS) Project at Oak Ridge National Laboratory (ORNL), it was determined that a hydrogen cold source should be retrofitted into an existing beam tube of the High Flux Isotope Reactor (HFIR) at ORNL> The preliminary design of this system has been completed and an approval in principal of the design has been obtained from the internal ORNL safety review committees and the US Department of Energy (DOE) safety review committee. The cold source concept is basically a closed loop forced flow supercritical hydrogen system. The supercritical approach was chosen because of its enhanced stability in the proposed high heat flux regions. Neutron and gamma physics of the moderator have been analyzed using the 3D Monte Carlo code MCNP. A 3D structural analysis model of the moderator vessel, vacuum tube, and beam tube was completed to evaluate stress loadings and to examine the impact of hydrogen detonations in the beam tube. A detailed ATHENA system model of the hydrogen system has been developed to simulate loop performance under normal and off-normal transient conditions. Semi-prototypic hydrogen loop tests of the system have been performed at the Arnold Engineering Design Center (AEDC) located in Tullahoma, Tennessee to verify the design and benchmark the analytical system model. A 3.5 kW refrigerator system has been ordered and is expected to be delivered to ORNL by the end of this calendar year. The present schedule shows the assembling of the cold source loop on side during the fall of 1999 for final testing before insertion of the moderator plug assembly into the reactor beam tube during the end of the year 2000.

Technologies in Reactor Safety, Fluid-structure Interaction, Sloshing and Natural Hazards Engineering

Technologies in Reactor Safety, Fluid-structure Interaction, Sloshing and Natural Hazards Engineering PDF Author: Shih-Jung Chang
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 338

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Book Description
Thirty-six contributions from the July 1998 Conference present an analysis of dynamic systems and fluid-structure interaction in reactor technology and fluid-structure interaction. Most of the papers reflect how advances in these fields of research, as a result of the development of high-performance computers and methods of experiment, lead to detailed results that could not have otherwise been obtained. Topics are divided into two sections--technologies in reactor safety and natural hazards engineering, and fluid-structure interaction and sloshing. Concludes with two student papers. Contains an author index but no subject index. Annotation copyrighted by Book News, Inc., Portland, OR

Transactions of the American Nuclear Society

Transactions of the American Nuclear Society PDF Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 952

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Book Description


Review

Review PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 580

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107-2 Hearings: Energy and Water Development Appropriations For 2003, Part 4, 2002, *

107-2 Hearings: Energy and Water Development Appropriations For 2003, Part 4, 2002, * PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 1512

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Energy and Water Development Appropriations for 2003

Energy and Water Development Appropriations for 2003 PDF Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 1440

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Energy and Water Development Appropriations for 2003: Department of Energy ... National Nuclear Security Administration ... Power Marketing Administrations

Energy and Water Development Appropriations for 2003: Department of Energy ... National Nuclear Security Administration ... Power Marketing Administrations PDF Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 2986

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The Liquid Hydrogen Moderator at the NIST Research Reactor

The Liquid Hydrogen Moderator at the NIST Research Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

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Book Description
In 1995, the NIST research reactor was shut down for a number of modifications, including the replacement of the D2O cold neutron source with a liquid hydrogen moderator. When the liquid hydrogen source began operating, the flux of cold neutrons increased by a factor of six over the D2O source. The design and operation of the hydrogen source are described, and measurements of its performance are compared with the Monte Carlo simulations used in the design. (auth).