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Criticality studies of interacting cylindrical systems

Description: From introduction: "As a part of this program, this report presents the results of a study of an interacting system in which the conditions for criticality are given in terms of the concentration of fissionable material and the geometry of the system."
Date: October 29, 1954
Creator: Miraldi, F. D.; Farquhar, J. & Perry, P. I.
Partner: UNT Libraries Government Documents Department

ELECTRONIC DATA PROCESSING, AN APPLICATION TO NUCLEAR MATERIALS MANAGEMENT

Description: The application of an electronic data processing system to the unique combination of scientific and commercial data processing requirements of nuclear materials management is discussed. The organization and ilow of data from the plant through the data processing equipment to the final report are discussed. Included are topics concerned with the impact of conversion to electronic data processing on personnel, materials management costs, and on other plant organizations. Portions are devoted to programming systems and decision-making abilities of data processing equipment which make these systems readily adaptable to nuclear materials management. (auth)
Date: October 31, 1963
Creator: Hudson, J F
Partner: UNT Libraries Government Documents Department

TWO-GROUP CONSTANTS FOR REACTOR MATERIALS

Description: In order to facilitate reactor design studies a compilation of calculated two-group constants averaged over the infinite-medium flux produced by a fission source was made for approximately 80 materials of interest to reactor engineers. A comparison with available experimental age measurements is included. (auth)
Date: May 1, 1958
Creator: Stanley, M.J.
Partner: UNT Libraries Government Documents Department

AN ANALYSIS OF POWER REACTOR FUEL REPROCESSING

Description: This report presents an analysis of the projected economies and processing capacity requirements for a power reactor fuel reprocessing industry based on the recovery of fertile and fissionable materials from presently proposed power reactors within tbe confines of the continental United 8tates for the next five to ten years. An analysis of the present general state of development of a technology required for such an Industry is given. A summary of results of power reactor reprocessing chemical and engineering development at Oak Ridge National Laboratory from July 1955 through December 1956 is given. (auth)
Date: March 27, 1957
Creator: Culler, F.L. Jr.; Blanco, R.E.; Goeller, H.E. & Watson, C.D.
Partner: UNT Libraries Government Documents Department

THE CALCULATION OF RADIAL TEMPERATURE DISTRIBUTIONS IN CYLINDRICAL FUEL SPECIMENS DURING NEUTRON IRRADIATION. Metallurgy Program 6.1.26

Description: A knowledge of the temperature distribution within a fuel sample during irradiation is required in order to evaluate the changes that occur in the physical and metallurgical propertoies of a fuel material upon irradiation. Because it is often impractical to measure temperatures within a fuel sample during irradiation, it is frequently necessary to rely upon computed values of the temperature. Therefore, a brief description and a comparison of the methods most frequently used for computing radial temperature distributions within irradiation samples are presented. The calculation of temperature distributions in samples containing fissionable isotopes is complicated by a number of variables, among which are the variation of heat production throughout the sample (due to local neutron-flux perturbations) and the variation of thermal conductivity occasioned by unusually steep temperature gradients. Various assumptions, which are considered to fit most closely the conditions at hand, are made for these calculations. As no standard set of assumptions can fit all cases, four illustrative cases are presented, representing four different sets of conditions applied to the heatconduction equation. The four cases considered may be briefly described as follows: varlable thermal conductivity, nonuniform heat production; variable thermal conductivity, uniform heat production; constant thermal conductivity, nonuniform heat production; and constant thermal conductivity, uniform heat production. (auth)
Date: November 1, 1958
Creator: Taraba, F.R.
Partner: UNT Libraries Government Documents Department

Preparation of fission foils for fission ionization chambers using a painting technique

Description: Fission foils for use in fission ionization chambers were produced by painting metal substrates with coats of fissionable isotopes. Areal densities as large as 2.0 mg/cm/sup 2/ were obtained with excellent adhesion. This painting technique has been successful in depositing isotopes of uranium, plutonium, americium, and curium on metal substrates made of beryllium, aluminum, copper, and nickel. The cost of this painting technique is estimated to be approximately one-tenth the cost of producing foils by evaporation, electrodeposition, or sputtering techniques. In addition, the painting technique is highly efficient, thereby minimizing waste of the available fissionable material. (auth)
Date: November 14, 1973
Creator: Behrens, J.W.
Partner: UNT Libraries Government Documents Department

Westinghouse Hanford Company special nuclear material vault storage study

Description: Category 1 and 2 Special Nuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs.
Date: April 23, 1996
Creator: Borisch, R.R.
Partner: UNT Libraries Government Documents Department

Nuclear Criticality Safety Evaluation of the 9965, 9968, 9972, 9973, 9974, and 9975 Shipping Casks

Description: A Nuclear Criticality Safety Evaluation (NCSE) has been performed for the 9965, 9968, 9972, 9973, 9974, and 9975 SRS-designed shipping casks. This was done in support of the recertification effort for the 9965 and 9968, and the certification of the newly designed 9972-9975 series. The analysis supports the use of these packages as Fissile Class I for shipment of fissionable material from the SRS FB-Line, HB-Line, and from Lawrence Livermore national Laboratory. six different types of material were analyzed with varying Isotopic composition, of both oxide and metallic form. The mass limits required to support the fissile Class I rating for each of the envelopes are given in the Table below. These mass limits apply if DOE approves an exception as described in 10 CFR 71.55(c), such that water leakage into the primary containment vessel does not need to be considered in the criticality analysis. If this exception is not granted, the mass limits are lower than those shown below. this issue is discussed in detail in sections 5 and 6 of the report.One finding from this work is important enough to highlight in the abstract. The fire tests performed for this family of shipping casks indicates only minimal charring of the Celotex thermal insulation. Analysis of the casks with no Celotex insulation (assuming it has all burned away), results in values of k-eff that exceed 1.0. Therefore, the Celotex insulation must remain intact in order to guarantee sub criticality of the 9972-9975 family of shipping casks.
Date: February 26, 1999
Creator: Frost, R.L.
Partner: UNT Libraries Government Documents Department

Preliminary evaluation of a fluorescence and radioisotope nuclear smuggling deterrence tag - final report (IL500E)

Description: This report summarizes the efforts completed in identifying candidate fluorescence compounds and radioisotopes for a developing tagging system. The tagging system is being developed as a deterrent to nuclear smuggling, by providing a means of: (1) tracing materials and pilferers to the facility of origin for any recovered special nuclear materials, (2) inventory control of long-term stored items containing special nuclear materials, and (3) tracking materials transferred between facilities. The system uses three types of materials to cover a range of applications intended to prevent the pilfering of special nuclear materials. One material, fluorescent compounds which are invisible without ultraviolet or near-infrared detection systems, is marked on controlled items with a tracking pattern that corresponds to a specified item in a specified location in the data control system. The tagging system uses an invisible, fluorescent dusting powder to mark equipment and personnel who inappropriately handle the tagged material. The tagging system also uses unique combinations of radionuclides to identify the facility of origin for any special nuclear material. This report also summarizes the efforts completed in identifying hardware that will be used for the tagging system. This hardware includes the devices for applying the tagging materials, the commercially available fluorescence detection systems, and gamma ray detection systems assembled from existing, commercially available technologies.
Date: April 1, 1997
Creator: Hartenstein, S.D.; Aryaeinejad, R. & Delmastro, J.R.
Partner: UNT Libraries Government Documents Department

Final Deactivation Project report on the Alpha Powder Facility, Building 3028, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: This report documents the condition of the Alpha Powder Facility (APF), Building 3028, after completion of deactivation activities. Activities conducted to place the facility in a safe and environmentally sound condition for transfer to the U.S. Department of Energy (DOE) Office of Environmental Restoration (EM-40) program are outlined. A history and profile of the facility prior to commencing deactivation activities and a profile of the building after completion of deactivation activities are provided. Turnover items, such as the post-deactivation surveillance and maintenance (S&M) plan, remaining hazardous materials, radiological controls, safeguards and security, quality assurance, facility operations, and supporting documentation provided for in the DOE Nuclear Materials and Facility Stabilization Program (EM-60) turnover package are discussed.
Date: April 1, 1997
Partner: UNT Libraries Government Documents Department

Analytic and experimental validation of thermo elastic plastic material response calculation

Description: We compare the thermo-elastic-plastic response of fissionable metals calculated by the solid mechanics code DYNA to an analytic model for the case of a uniformly heated thin spherical shell and to experimental data for the case of a thin rod heated in a pulsed reactor. In both cases, the materials are volumetrically heated by neutron exposure. We find good agreement between the code and the analytic model and experimental data for the first and second case, respectively. For very fast heating times, macroscopic displacement may be replaced by microscopic plastic flow. To verify this behavior, an experiment to be done at SNLA SPR III is described. Validation of the code in these simple geometries is a necessary step if calculations involving more complicated geometries are to be understood and trusted.
Date: October 2, 1997
Creator: DiPeso, G.
Partner: UNT Libraries Government Documents Department

Estimates of fission yields in nuclear criticality excursions

Description: There is a need for computer simulation of hypothetical criticality excursions involving significant quantities of fissionable materials, especially in fissile aqueous system. The need arises due to the requirements for the emergency planning of facilities where the fissionable materials are handled, processed, or stored; and the regulatory requirements associated with facility operation or conversion. It is proposed here that a data base of fission yeilds for critical experiments and known accidents (both aqueous and solid) should be generated by using existing or new computer codes. The success in compiling this data base would provide useful source-terms for criticality excursions, realistic estimates of emergency-response boundary, as well as a replacement for the ``rule-of-thumb`` or ``bounding`` method. 10 refs.
Date: June 1, 1995
Creator: Choi, J.S.; Thompson, J.W. & Reed, R.
Partner: UNT Libraries Government Documents Department

Real-time software use in nuclear materials handling criticality safety control

Description: This paper addresses the use of real-time software to assist handlers of fissionable nuclear material. We focus specifically on the issue of workstation mass limits, and the need for handlers to be aware of, and check against, those mass limits during material transfers. Here ``mass limits`` generally refer to criticality safety mass limits; however, in some instances, workstation mass limits for some materials may be governed by considerations other than criticality, e.g., fire or release consequence limitation. As a case study, we provide a simplified reliability comparison of the use of a manual two handler system with a software-assisted two handler system. We identify the interface points between software and handlers that are relevant to criticality safety.
Date: June 1, 1997
Creator: Huang, S.; Lappa, D.; Chiao, T.; Parrish, C.; Carlson, R.; Lewis, J. et al.
Partner: UNT Libraries Government Documents Department

Environmental assessment for consolidation of certain materials and machines for nuclear criticality experiments and training

Description: In support of its assigned missions and because of the importance of avoiding nuclear criticality accidents, DOE has adopted a policy to reduce identifiable nuclear criticality safety risks and to protect the public, workers, government property and essential operations from the effects of a criticality accident. In support of this policy, the Los Alamos Critical Experiments Facility (LACEF) at the Los Alamos National Laboratory (LANL) Technical Area (TA) 18, provides a program of general purpose critical experiments. This program, the only remaining one of its kind in the United States, seeks to maintain a sound basis of information for criticality control in those physical situations that DOE will encounter in handling and storing fissionable material in the future, and ensuring the presence of a community of individuals competent in practicing this control.
Date: May 21, 1996
Partner: UNT Libraries Government Documents Department

CSER 00-008 use of PFP Glovebox HC-18BS for Storage and Transport of Fissionable Material

Description: This CSER addresses the feasibility of increasing the allowed number of open containers and permitting the transfer and storage of fissionable material in Glovebox HC-18BS without regard to form or density (metal, oxide having an H/X {le} 20, material having unrestricted moderation and plutonium hydroxide having a plutonium density of 0.2 g/cm{sup 3}).
Date: June 1, 2000
Creator: ERICKSON, D.G.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Effective Multiplication Factors for Bare Cylinders

Description: Report issued by the Atomic Energy Commission over computer-aided calculations for effective multiplication factors in cylinders. The methods, and applications of the calculations are discussed. This report includes tables, and illustrations.
Date: May 1962
Creator: Lanes, Stephen J.
Partner: UNT Libraries Government Documents Department