HFIR Cold Neutron Source Moderator Vessel Design Analysis

HFIR Cold Neutron Source Moderator Vessel Design Analysis PDF Author:
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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:
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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:
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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.

Physics Analyses in the Design of the HFIR Cold Neutron Source

Physics Analyses in the Design of the HFIR Cold Neutron Source PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

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Book Description
Physics analyses have been performed to characterize the performance of the cold neutron source to be installed in the High Flux Isotope Reactor at the Oak Ridge National Laboratory in the near future. This paper provides a description of the physics models developed, and the resulting analyses that have been performed to support the design of the cold source. These analyses have provided important parametric performance information, such as cold neutron brightness down the beam tube and the various component heat loads, that have been used to develop the reference cold source concept.

Materials Selection for the HFIR Cold Neutron Source

Materials Selection for the HFIR Cold Neutron Source PDF Author:
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ISBN:
Category :
Languages : en
Pages : 5

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Book Description
In year 2002 the High Flux Isotope Reactor (HFIR) will be fitted with a source of cold neutrons to upgrade and expand its existing neutron scattering facilities. The in-reactor components of the new source consist of a moderator vessel containing supercritical hydrogen gas moderator at a temperature of 20K and pressure of 15 bar, and a surrounding vacuum vessel. They will be installed in an enlarged beam tube located at the site of the present horizontal beam tube, HB-4; which terminates within the reactor's beryllium reflector. These components must withstand exceptional service conditions. This report describes the reasons and factors underlying the choice of 6061-T6 aluminum alloy for construction of the in-reactor components. The overwhelming considerations are the need to minimize generation of nuclear heat and to remove that heat through the flowing moderator, and to achieve a minimum service life of about 8 years coincident with the replacement schedule for the beryllium reflector. 6061-T6 aluminum alloy offers the best combination of low nuclear heating, high thermal conductivity, good fabricability, compatibility with hydrogen, superior cryogenic properties, and a well-established history of satisfactory performance in nuclear environments. These features are documented herein. An assessment is given of the expected performance of each component of the cold source.

The Design and Construction of a Cold Neutron Source for Use in the Cornell University Triga Reactor

The Design and Construction of a Cold Neutron Source for Use in the Cornell University Triga Reactor PDF Author: Lydia Jane Young
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 282

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Thermal-hydraulic Studies of the Advanced Neutron Source Cold Source

Thermal-hydraulic Studies of the Advanced Neutron Source Cold Source PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 37

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Book Description
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.

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


Some Preliminary Design Considerations for the ANS (Advanced Neutron Source) Reactor Cold Source

Some Preliminary Design Considerations for the ANS (Advanced Neutron Source) Reactor Cold Source PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Book Description
Two areas concerned with the design of the Advanced Neutron Source (ANS) cold source have been investigated by simple one-dimensional calculations. The gain factors computed for a possible liquid nitrogen-15 cold source moderator are considerably below those computed for the much colder liquid deuterium moderator, as is reasonable considering the difference in moderator temperature. Nevertheless, nitrogen-15 does represent a viable option should safety related issues prohibit the use of deuterium as a moderating material. The slab geometry calculations have indicated that reflection of neutrons may be the dominant moderating mechanism and should be a consideration in the design of the cold source. 9 refs., 2 figs.