Abstract
The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past two years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 by utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. Preliminary studies have identified several potential approaches to the ACPR performance improvement. The most promising approach appears to be the two-region core concept. The inner region, surrounding the irradiation cavity, would consist of a high-heat capacity fuel capable of absorbing the fission energy associated with a
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Reuscher, J A
[1]
- Sandia Laboratories, Albuquerque, NM (United States)
Citation Formats
Reuscher, J A.
Upgrade of the Annular Core Pulse Reactor.
United States: N. p.,
1976.
Web.
Reuscher, J A.
Upgrade of the Annular Core Pulse Reactor.
United States.
Reuscher, J A.
1976.
"Upgrade of the Annular Core Pulse Reactor."
United States.
@misc{etde_21152782,
title = {Upgrade of the Annular Core Pulse Reactor}
author = {Reuscher, J A}
abstractNote = {The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past two years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 by utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. Preliminary studies have identified several potential approaches to the ACPR performance improvement. The most promising approach appears to be the two-region core concept. The inner region, surrounding the irradiation cavity, would consist of a high-heat capacity fuel capable of absorbing the fission energy associated with a large nuclear pulse. The number of fissions occurring near the cavity would be greatly increased which, in turn, would significantly increase the fluence in the cavity. The outer region would consist of a U-ZrH fuel to provide an overall negative temperature coefficient for the two region core. Two candidate high heat capacity fuels [(BeO-UO{sub 2} and UC-ZrC) - graphite] are under consideration. Since this reactor upgrade represents a modification to an existing facility, it can be achieved in a relatively short time. It is anticipated that most of the existing reactor structure can be used for the upgrade. The present core occupies about one-half of the location in the grid plate. The high-heat capacity fuel elements will occupy the three rings adjacent to the irradiation cavity and the U-ZrH elements will be placed in the four outer rings. Other modifications are anticipated for the reactor systems. A completely new control system will be installed, a larger pool cooling capability is required for a higher steady-state power, and the need for a containment system is anticipated in the event of a reactor accident. Another part of the fast reactor safety research program at Sandia Laboratories is the investigation of techniques to observe the motion of molten fuel and clad during and after a reactor pulse. Such a device may require changes to the grid configuration so that a radial row of fuel elements can be removed to allow observation of an experiment in the cavity. Core design considerations for a fuel motion detection system are a part of the upgrade project. (author)}
place = {United States}
year = {1976}
month = {Jul}
}
title = {Upgrade of the Annular Core Pulse Reactor}
author = {Reuscher, J A}
abstractNote = {The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past two years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 by utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. Preliminary studies have identified several potential approaches to the ACPR performance improvement. The most promising approach appears to be the two-region core concept. The inner region, surrounding the irradiation cavity, would consist of a high-heat capacity fuel capable of absorbing the fission energy associated with a large nuclear pulse. The number of fissions occurring near the cavity would be greatly increased which, in turn, would significantly increase the fluence in the cavity. The outer region would consist of a U-ZrH fuel to provide an overall negative temperature coefficient for the two region core. Two candidate high heat capacity fuels [(BeO-UO{sub 2} and UC-ZrC) - graphite] are under consideration. Since this reactor upgrade represents a modification to an existing facility, it can be achieved in a relatively short time. It is anticipated that most of the existing reactor structure can be used for the upgrade. The present core occupies about one-half of the location in the grid plate. The high-heat capacity fuel elements will occupy the three rings adjacent to the irradiation cavity and the U-ZrH elements will be placed in the four outer rings. Other modifications are anticipated for the reactor systems. A completely new control system will be installed, a larger pool cooling capability is required for a higher steady-state power, and the need for a containment system is anticipated in the event of a reactor accident. Another part of the fast reactor safety research program at Sandia Laboratories is the investigation of techniques to observe the motion of molten fuel and clad during and after a reactor pulse. Such a device may require changes to the grid configuration so that a radial row of fuel elements can be removed to allow observation of an experiment in the cavity. Core design considerations for a fuel motion detection system are a part of the upgrade project. (author)}
place = {United States}
year = {1976}
month = {Jul}
}