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Hot Fuel Examination Facility's neutron radiography reactor

Description: Argonne National Laboratory-West is located near Idaho Falls, Idaho, and is operated by the University of Chicago for the United States Department of Energy in support of the Liquid Metal Fast Breeder Reactor Program, LMFBR. The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both nondestructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the nondestructive examination techniques utilized at HFEF is neutron radiography, which is provided by the NRAD reactor facility (a TRIGA type reactor) below the HFEF hot cell.
Date: January 1, 1983
Creator: Pruett, D.P.; Richards, W.J. & Heidel, C.C.
Partner: UNT Libraries Government Documents Department

Neutronics analysis of the proposed 25-MW leu TRIGA Multipurpose Research Reactor

Description: More than two years ago the government of Indonesia announced plans to purchase a research reactor for the Puspiptek Research Center in Serpong Indonesia to be used for isotope production, materials testing, neutron physics measurements, and reactor operator training. Reactors using low-enriched uranium (LEU) plate-type and rod-type fuel elements were considered. This paper deals with the neutronic evaluation of the rod-type 25-MW LEU TRIGA Multipurpose Research Reactor (MPRR) proposed by the General Atomic Company of the United States of America.
Date: 1982-23~
Creator: Nurdin, M.; Bretscher, M. M. & Snelgrove, J. L.
Partner: UNT Libraries Government Documents Department

New neutron simulation capabilities provided by the Sandia Pulse Reactor (SPR-III) and the Upgraded Annular Core Pulse Reactor (ACPR)

Description: The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the radiation hardening of advanced nuclear weapon systems. Emphasis is placed upon two new reactor simulation sources; the Sandia Pulse Reactor-III (SPR-III) Facility which enhances the neutron exposure volume capabilities over those presently available with the existing SPR-II Facility, and the Upgraded Annular Core Pulse Reactor (ACPR) Facility which enhances the neutron exposure capabilities over those of the former ACPR Facility.
Date: July 1, 1978
Creator: Choate, L.M. & Schmidt, T.R.
Partner: UNT Libraries Government Documents Department

Neutron flux enhancement in the NRAD reactor

Description: In 1987 a series of experiments were conducted at the NRAD reactor facility at Argonne National Laboratory - West (ANL-W) to investigate the possibility of increasing the thermal neutron content at the end of the reactor's east beam tube through the use of hydrogenous flux traps. It was desired to increase the thermal flux for a series of experiments to be performed in the east radiography cell, in which the enhanced flux was required in a relatively small volume. Hence, it was feasible to attempt to focus the cross section of the beam to a smaller area. Two flux traps were constructed from unborated polypropylene and tested to determine their effectiveness. Both traps were open to the entire cross-sectional area of the neutron beam (as it emerges from the wall and enters the beam room). The sides then converged such that at the end of the trap the beam would be 'focused' to a greater intensity. The differences in the two flux traps were primarily in length, and hence angle to the beam as the inlet and outlet cross-sectional areas were held constant. It should be noted that merely placing a slab of polypropylene in the beam will not yield significant multiplication as neutrons are primarily scattered away.
Date: January 1, 1988
Creator: Weeks, A.A.; Heidel, C.C. & Imel, G.R.
Partner: UNT Libraries Government Documents Department

Neutron radiography at the NRAD facility

Description: The NRAD facility uses a 150 kW TRIGA reactor as a source of neutrons and is integrated with a hot cell such that highly radioactive specimens can be radiographed without removing them from the hot cell environment. A second beam tube is located in a separate shielded addition to HFEF and permits neutron radiography of irradiated or unirradiated specimens without subjecting them to the alpha-contaminated hot cell environment. Both beams are optimized for neutron radiography of highly radioactive nuclear fuels. Techniques for using these facilities are described. Advantages include: the ability to perform thermal and epithermal neutron radiography on specimens either inside or outside the hot cell, lack of competition for the use of the reactor, versatility of facility design, and the addition of neutron tomography. (LEW)
Date: January 1, 1984
Creator: McClellan, G.C. & Richards, W.J.
Partner: UNT Libraries Government Documents Department

Reconfiguration of the NRAD delay loop for proposed 1 MW operations

Description: The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both nondestructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the nondestructive examination technqiues utilized at HFEF is neutron radiography. Neutron radiography is provided by the NRAD reactor facility, which is located beneath the HFEF hot cell. The NRAD reactor is a TRIGA reactor and is operated at a steady-state power level of 250 kw solely for neutron radiography and the development of radiography techniques. Modifications of the NRAD delay loop for 1 MW operations are described.
Date: January 1, 1984
Creator: Heidel, C.C.; Richards, W.J. & Pruett, D.P.
Partner: UNT Libraries Government Documents Department

Proposed power upgrade of the Hot Fuel Examination Facility's neutron radiography reactor. [NRAD reactor]

Description: The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both non-destructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the non-destructive examination techniques utilized at HFEF is neutron radiography. Neutron radiography is provided by the NRAD reactor facility, which is located beneath the HFEF hot cell. The NRAD reactor is a TRIGA reactor and is operated at a steady state power level of 250 kW solely for neutron radiography and the development of radiography techniques. When the NRAD facility was designed and constructed, an operating power level of 250 kW was considered to be adequate for obtaining radiographs of the type of specimens envisaged at that time. A typical radiograph required approximately a twenty-minute exposure time. Specimens were typically single fuel rods placed in an aluminum tray. Since that time, however, several things have occurred that have tended to increase radiography exposure times to as much as 90 minutes each. In order to decrease exposure times, the reactor power level is to be increased from 250 kw to 1 MW. This increase in power will necessitate several engineering and design changes. These changes are described.
Date: January 1, 1984
Creator: Pruett, D.P.; Richards, W.J. & Heidel, C.C.
Partner: UNT Libraries Government Documents Department

Oregon State University TRIGA Reactor annual report

Description: The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.
Date: August 31, 1979
Creator: Anderson, T.V.; Johnson, A.G.; Bennett, S.L. & Ringle, J.C.
Partner: UNT Libraries Government Documents Department

Remote encapsulation of mixed-oxide fuel pellets for transient testing

Description: Nine individual fuel pellets from irradiated fuel pins were extracted and encapsulated remotely in double containment canisters in support of the simulated loss-of-coolant flow tests being conducted in the Sandia Laboratory Annular Core Pulsed Reactor.
Date: January 1, 1978
Creator: Dowler, K.E.; Newbury, F.H.; Ledbetter, J.M. & Cano, G.L.
Partner: UNT Libraries Government Documents Department

Annular Core Pulse Reactor upgrade quarterly report, January--March 1977

Description: Information is presented concerning safety, compliance, and documentation; core nuclear design; ACPR upgrade and console development; mechanical design; fuel element design; fuel element fabrication; secondary fuel materials studies; driver core fuel element; and diagnostic system.
Date: June 1, 1977
Creator: Walker, J. V.
Partner: UNT Libraries Government Documents Department

Circuit designs for measuring reactor period, peak power, and pulse fluence on TRIGA and other pulse reactors

Description: Inexpensive circuits for use in evaluating reactor periods, peak power, and pulse fluence (NVT), are presented. Besides being low in cost, these circuits are easily assembled and calibrated, and operate with a high degree of accuracy. The positive period measuring system has been used in evaluating reactivity additions as small as 5 cents (with an accuracy of +-0.1 cent) and as large as $4.50 (accuracy +-2 cents). Reactor peak power is measured digitally with a system accuracy of +-0.1% of a 10 volt input (+-10 mV). The NVT circuit measures over a 2/sup 1///sub 2/ decade range, has 3-place resolution, and an accuracy of better than 1%.
Date: August 1, 1977
Creator: Meyer, R. D.; Thome, F. V. & Williams, R. L.
Partner: UNT Libraries Government Documents Department