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Nuclear safety guide TID-7016 Revision 2

Description: The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nu… more
Date: January 1, 1980
Creator: Thomas, J T
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental program to validate analyses of accelerator breeder concepts

Description: The concept of using high-energy particle accelerators to produce neutrons for converting fertile material to fissile is over 25 years old. It is only relatively recently that accelerator design has progressed to a point where the operation approaches commercial viability. Critical unknowns in the concept were identified in a detailed study of specic configurations. Experiments to elucidate these unknowns in a timely manner using existing material and facilities are defined and identified. Basi… more
Date: January 1, 1977
Creator: Talbert Jr., W. L.; Russell, G. J. & Malenfant, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Linear accelerator driven (LADR) and regenerative reactors (LARR) for nuclear non-proliferation

Description: Linear accelerator breeders (LAB) could be used to produce fissile fuel in two modes, either with fuel reprocessing or without fuel reprocessing. With fuel reprocessing, the fissile material would be separated from the target and refabricated into a fuel element for use in a burner power reactor. Without reprocessing, the fissile material would be produced in-situ, either in a fresh fuel element or in a depleted or burned element after use in a power reactor. In the latter mode the fissile mate… more
Date: September 1, 1977
Creator: Steinberg, M.; Takahashi, H.; Powell, J. R. & Kouts, H. J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary report on the promise of accelerator-driven natural-uranium-fueled light-water-moderated breeding power reactors

Description: A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power.… more
Date: July 1, 1977
Creator: Greenspan, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38

Description: An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: April 1, 1978
Creator: Klima, B. B.; Shappert, L. B.; Seagren, R. D. & Box, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Isotopic distributions, element ratios, and element mass fractions from enrichment-meter-type gamma-ray measurements of MOX

Description: The gamma-ray spectra from infinitely'' thick mixed oxide samples have been measured. The plutonium isotopics, the U/Pu ratio, the high-Z mass fractions (assuming only plutonium, uranium, and americium), and the low-Z mass fraction (assuming the matrix is only oxygen) can be determined by carefully analyzing the data. The results agree well with the chemical determination of these parameters. 8 refs., 3 figs., 3 tabs.
Date: January 1, 1991
Creator: Close, D. A.; Parker, J. L.; Haycock, D. L. & Dragnev, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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First-year evaluation of a nondestructive assay system for the examination of ORNL TRU waste

Description: The Oak Ridge National Laboratory has been selected as the demonstration site for a new transuranic neutron assay system (NAS) developed at the Los Alamos National Laboratory. In addition, in order to meet specific ORNL program objectives, an upgraded segmented gamma-ray drum scanner has been integrated into the nondestructive assay (NDA) system to serve as a radioisotope identifier and as a quantitative assay backup to the NAS. A verification study, wherein selected waste drums will be emptied… more
Date: April 1, 1984
Creator: Schultz, F. J.; Haff, K. W.; Coffey, D. E.; Norris, L. B.; Caldwell, J. T.; Close, D. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rod scanner assay of FFTF fuel

Description: Rod scanner results for over 40,000 FFTF Cores 1 and 2 fuel pins are summarized. An improved rod scanner calibration technique for FFTF Cores 3 and 4 fuel pins is described. Data are compared with chemical assay measurements. 5 fig., 5 tables.
Date: January 1, 1978
Creator: Goris, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials technology for accelerator production of fissile isotopes

Description: The materials used for the accelerator production of fissile isotopes must enable the facility to achieve maximum fuel production at a minimum cost. Neutron production in the target would be maximized by use of thorium cooled with Pb--56 percent Bi or with sodium. The thorium should be ion-plated with approximately 1 mil of nickel or stainless steel for retention of fission products. The target container will have to be replaced at frequent intervals because of the copious quantities of neutron… more
Date: February 1, 1978
Creator: Horak, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-sensitivity transuranic waste assay by simultaneous proton and thermal-neutron interrogation using an electron linear accelerator

Description: Simultaneous photon and neutron interrogation from electron linear accelerator pulses is used as the basis for a unique assay technique for transuranics. Both prompt and delayed neutrons from the induced fissions are counted on a single detection system, and the contributions from each interrogating flux are resolved. Detection limits (3 sigma) for /sup 239/Pu were estimated to be 3 mg for prompt fission neutrons and 6 mg for delayed neutrons. The technique also provides a clear distinction bet… more
Date: January 1, 1982
Creator: Franks, L. A.; Pigg, J. L.; Caldwell, J. T.; Cates, M. R.; Kunz, W. E. & Noel, B. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experimental evaluation of the differential die-away pulsed-neutron technique for the fissile assay of hot irradiated fuel waste

Description: Hot irradiated fuel waste packages containing self neutron sources up to 10/sup 7/ n/s may be assayed successfully with a 25-mg /sup 239/Pu detection sensitivity using a differential die-away fissile assay system based on a Sandia-designed 14-MeV neutron generator. With a minor design change, our system can accommodate contact gamma dose rates up to 10/sup 4/ R/h with no loss of fissile assay sensitivity.
Date: January 1, 1982
Creator: Caldwell, J.T. & Kunz, W.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety analysis report for packaging: the ORNL loop transport cask

Description: An evaluation of the ORNL loop transport cask demonstrating its compliance with the regulations governing the transportation of radioactive and fissile materials is presented. A previous review of the cask is updated to demonstrate compliance with current regulations, to present current procedures, and to reflect the more recent technology.
Date: November 1, 1977
Creator: Evans, J. H.; Chipley, K. K.; Nelms, H. A.; Crowley, W. K. & Just, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unit cell simulation for cylinders on a triangular pitch

Description: In this paper we analyze the use of these equivalent unit cells for two problem-types of interest: a infinite lattice of small-diameter fuel pins and an infinite array of large shipping containers. Both void and water are considered as interstitial materials between the cylindrical units. The fuel pins modeled are uranium nitride pins clad with tantalum and niobium with a diameter of 1.1 cm. The pins are infinitely long. The shipping container model is a 55 gallon drum with 13 cm thick insulati… more
Date: January 1, 1991
Creator: O'Dell, R. D. & Schlesser, J. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Quantitative study of mixing in annular and raschig ring filled tanks

Description: A quantitative study of mixing, which utilized the exit age distribution theory, has been completed for bench-scale annular and raschig ring filled tanks, in addition to a pilot-scale annular tank. A study of mixing and fluid flow in a full-scale, single-entry, raschig ring filled tank also was initiated. Results showed the bench-scale raschig ring filled tank approached plug-flow (no mixing) behavior. In a bench-scale annular tank, regardless of whether fluid entered tangentially or nontangent… more
Date: July 14, 1980
Creator: Fredrickson, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary talk covering application-oriented sessions

Description: Some progress is mentioned in nuclear data, including: nonfuel actinide cross sections, fusion charged particle reactions, lithium-7 breakup reaction, neutrons per fission, decay heat from fission products, the form of the fission spectrum, and neutron scattering differential cross sections. Trends are then identified, particularly N(E,t) for delayed neutrons, internationally focussed efforts to resolve outstanding problems, dosimetry cross sections and techniques, fusion integral experiments, … more
Date: January 1, 1985
Creator: Peelle, R. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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High-velocity impact tests involving thin spherical shells of tantalum and 304 stainless steel

Description: This experimental program generated data to improve computer-code modeling of impact phenomena. The improved computation technique will be used to design a fissile-material container able to withstand a 335 m/s impact. The program involved flyer-plate-impact tests using thin shells of annealed 304 stainless steel and annealed tantalum at impact velocities of 28 to 180 m/s. No active instrumentation was used in this study; instead, all data were derived from measurements of test specimens. Pre- … more
Date: August 26, 1977
Creator: Steffan, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety Analysis Report for Packaging (SARP) for USA/9506/BLF (DOE-AL)

Description: The Safety Analysis Report for Packaging (SARP) satisfies the request of the U.S. Energy Research and Development Administration for a formal safety analysis of the insulated drum shipping container identified as USA/9506/BLF(DOE-A1). Included are discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Complete physical and technical descriptions of the packages are presented.
Date: November 11, 1977
Creator: Watkins, R. A.; Bertram, R. E.; Blauvelt, R. K.; Griffin, J. F.; Peterson, J. B. & Prosser, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NCIS - a Nuclear Criticality Information System (overview)

Description: A Nuclear Criticality Information System (NCIS) is being established at the Lawrence Livermore National Laboratory (LLNL) in order to serve personnel responsible for safe storage, transport, and handling of fissile materials and those concerned with the evaluation and analysis of nuclear, critical experiments. Public concern for nuclear safety provides the incentive for improved access to nuclear safety information.
Date: July 1, 1983
Creator: Koponen, B. L. & Hampel, V. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Coincidence logic modules for criticality alarming

Description: A coincidence Logic Module and a companion contact closure Relay Module utilizing the NIM Standard have been developed for criticality alarming. The units provide an ALARM whenever two or more out of N detectors become activated. In addition, an ALERT is generated whenever one or more detectors is activated or when certain electronic component failures occur. The number of detector inputs (N) can be expanded in groups of six by adding modules. Serial and parallel redundancy were used to reduce … more
Date: April 1, 1977
Creator: Schaief, C.C. III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma-Ray Measurements With the Segmented Gamma Scan. [Maintenance Manual]

Description: A revised and updated operation and maintenance manual for the segmented gamma-scan instrument is presented, which describes routine assay techniques as well as the theory of operation in sufficient depth that an experienced assayist can make nonroutine assays on a wide variety of materials and samples. In addition, complete electronic and electrical schematics of the Los Alamos Scientific Laboratory (LASL)-designed portions of the system are presented, along with sufficient system and circuit … more
Date: December 1, 1977
Creator: Martin, E. R.; Jones, D. F. & Parker, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2

Description: An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations. The package is designed to ship large qu… more
Date: April 1, 1978
Creator: Klima, B. B.; Shappert, L. B.; Seagren, R. D. & Box, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron inelastic-scattering cross sections of /sup 232/Th, /sup 233/U, /sup 235/U, /sup 238/U, /sup 239/Pu and /sup 240/Pu. [LMFBR]

Description: Differential-neutron-emission cross sections of /sup 232/Th, /sup 233/U, /sup 235/U, /sup 238/U, /sup 239/Pu and /sup 240/Pu are measured between approx. = 1.0 and 3.5 MeV with the angle and magnitude detail needed to provide angle-integrated emission cross sections to approx. < 3% accuracies. Emitted-neutron resolutions are quantitatively defined and vary from approx. = 0.1 to 0.35 MeV. The experimental results are corrected for fisson-neutron contributions to obtain pseudo-elastic-neutron-sca… more
Date: January 1, 1982
Creator: Smith, A. B. & Guenther, P. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In situ measurements of neutron multiplying systems

Description: Historical and recent examples of the application of in situ measurements to provide knowledge for specific operations and general criticality safety guidance are reviewed. The importance of the American National Standard, Safety in Conducting Subcritical Neutron-Multiplication Measurements In Situ, ANSI/ANS-8.6, 1988 is discussed. Examples of possible future applications of in-situ measurements are provided. 4 refs., 4 figs.
Date: January 1, 1989
Creator: McLaughlin, T.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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WSRC approach to validation of criticality safety computer codes

Description: Recent hardware and operating system changes at Westinghouse Savannah River Site (WSRC) have necessitated review of the validation for JOSHUA criticality safety computer codes. As part of the planning for this effort, a policy for validation of JOSHUA and other criticality safety codes has been developed. This policy will be illustrated with the steps being taken at WSRC. The objective in validating a specific computational method is to reliably correlate its calculated neutron multiplication f… more
Date: January 1, 1991
Creator: Finch, D.R. & Mincey, J.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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