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Radiation in the SLC final focus alcoves from beam losses in collimators and dumps. Revision

Description: There are various beam line components between the interaction point (IP) of the SLC and the beam dumps which will intercept enough beam to warrant calculating the radiation levels inside the final focus alcoves. The three types of devices which are of concern are the main dump, tune-up dumps, and adjustable collimators. Fluences of and doses from neutrons and photons in the alcoves are calculated. It is concluded that if the beam losses do occur as expected, many of the electronic components i… more
Date: October 1, 1986
Creator: Jenkins, T.M. & McCall, R.C.
Partner: UNT Libraries Government Documents Department
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Radiation in the SLC final focus alcoves from beam losses in collimators and dumps

Description: Radiation levels inside the final focus alcoves are calculated from the main dump, tune-up dumps, and adjustable collimators. Neutron calculations are done for giant resonance neutrons. Fluences of neutrons and photons in the alcoves are determined. It is concluded that, if the beam losses do indeed occur as believed, many of the electronic components in the alcoves will begin to fail after a very short running period. (LEW)
Date: September 10, 1986
Creator: Jenkins, T.M. & McCall, R.C.
Partner: UNT Libraries Government Documents Department
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Environmental monitoring at the Lawrence Livermore National Laboratory. 1985 annual report

Description: Results are reported of the Environmental Quality Verification Program, which is an expanded continuation of the program of environmental monitoring previously carried out by the Environmental Measurements Group of the Hazards Control Department. Data are reported on air, soils, water, vegetation, foodstuffs, and annual radiation doses at perimeter of facility.
Date: February 1, 1986
Creator: Griggs, K.S. & Buddemeier, R.W.
Partner: UNT Libraries Government Documents Department
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Investigation report of the release of strontium-90 from the Building 3517 Cell Ventilation Improvements construction site on November 29, 1985

Description: This Type B Investigative Report provides an evaluation of all relevant events and activities that led to, were an integral part of, and subsequently resulted from ORNL's November-December 1985 strontium-90 release incident. The impacts were evaluated in terms of radiological doses to ORNL and Rust employees associated with the incident, ORGDP employees who consumed potable water potentially impacted by the incident, and Kingston, Tennessee, residents who also consumed potable water potentially… more
Date: January 21, 1986
Partner: UNT Libraries Government Documents Department
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Preliminary Assessment of Radiological Doses in Alternative Waste Management Systems Without an MRS Facility

Description: This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the referen… more
Date: June 1, 1986
Creator: Schneider, K. J.; Pelto, P. J.; Daling, P. M.; Lavender, J. C. & Fecht, B. A.
Partner: UNT Libraries Government Documents Department
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Muon fluence measurements at the site boundary for 1985

Description: Muon fluence (muons cm/sup -2/) was measured downstream of the experimental area beamlines, just beyond the Fermilab site boundary at Route 38. The purpose of these measurements was to obtain an estimate of the yearly off-site radiation exposure to the general population due to accelerator-produced muons during the 1985 800 GeV run.
Date: March 1, 1986
Creator: Elwyn, A.J.
Partner: UNT Libraries Government Documents Department
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Safety analysis of the existing 851 Firing Facility

Description: A safety analysis was performed to determine if normal operations and/or potential accidents at the 851 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but two of the hazards were either low or of the type or magnitud… more
Date: June 5, 1986
Creator: Odell, B.N.
Partner: UNT Libraries Government Documents Department
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Weldon Spring historical dose estimate

Description: This study was conducted to determine the estimated radiation doses that individuals in five nearby population groups and the general population in the surrounding area may have received as a consequence of activities at a uranium processing plant in Weldon Spring, Missouri. The study is retrospective and encompasses plant operations (1957-1966), cleanup (1967-1969), and maintenance (1969-1982). The dose estimates for members of the nearby population groups are as follows. Of the three periods … more
Date: July 1, 1986
Creator: Meshkov, N.; Benioff, P.; Wang, J. & Yuan, Y.
Partner: UNT Libraries Government Documents Department
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Occupational dose estimates for a monitored retrievable storage facility

Description: Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. Th… more
Date: June 1, 1986
Creator: Harty, R. & Stoetzel, G.A.
Partner: UNT Libraries Government Documents Department
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Dosimetry of x-ray beams: The measure of the problem

Description: This document contains the text of an oral presentation on dosimetry of analytical x-ray equipment presented at the Denver X-Ray Conference. Included are discussions of sources of background radiation, exposure limits from occupational sources, and the relationship of these sources to the high dose source of x-rays found in analytical machines. The mathematical basis of x-ray dosimetry is reviewed in preparation for more detailed notes on personnel dosimetry and the selection of the most approp… more
Date: August 1, 1986
Creator: de Castro, T.M.
Partner: UNT Libraries Government Documents Department
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PRESTO-II: a low-level waste environmental transport and risk assessment code

Description: PRESTO-II (Prediction of Radiation Effects from Shallow Trench Operations) is a computer code designed for the evaluation of possible health effects from shallow-land and, waste-disposal trenches. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuing exposure, and health impacts to a static local population for a 1000-year period following the end of disposal operations. Human exposure scenarios considered include normal releases (in… more
Date: April 1, 1986
Creator: Fields, D. E.; Emerson, C. J.; Chester, R. O.; Little, C. A. & Hiromoto, G.
Partner: UNT Libraries Government Documents Department
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Gamma-N activation of cancer patients

Description: High energy gamma radiation (8 to 30 MeV) is gaining acceptance for radiation therapy of patients with deep cancers. This radiation is of sufficient energy to induce photonuclear activation of the elements in the human body. Our results of measurements of nitrogen and phosphorus in an anthropomorphic phantom, a cadaver, and a cancer patient with bremsstrahlung radiation from 15 MeV electrons demonstrate the feasibility of a method to monitor these two elements in the human body in vivo by measu… more
Date: January 1, 1986
Creator: Wielopolski, L.; Meek, A.G.; Moskowitz, M. & Cohn, S.H.
Partner: UNT Libraries Government Documents Department
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Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

Description: The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Sce… more
Date: February 1, 1986
Creator: Mishima, J.; Sutter, S. L.; Hawley, K. A.; Jenkins, C. E. & Napier, B. A.
Partner: UNT Libraries Government Documents Department
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DITTY - a Computer Program for Calculating Population Dose Integrated Over Ten Thousand Years

Description: The computer program DITTY (Dose Integrated Over Ten Thousand Years) was developed to determine the collective dose from long term nuclear waste disposal sites resulting from the ground-water pathways. DITTY estimates the time integral of collective dose over a ten-thousand-year period for time-variant radionuclide releases to surface waters, wells, or the atmosphere. This document includes the following information on DITTY: a description of the mathematical models, program designs, data file … more
Date: March 1, 1986
Creator: Napier, B. A.; Peloquin, R. A. & Strenge, D. L.
Partner: UNT Libraries Government Documents Department
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Proposal for a new tomographic device providing information on the chemical properties of a body section

Description: A system to analyze the chemical properties of a region of tissue located deep inside the human body without having to access it is proposed. The method is based on a high precision detection of x-rays or ..gamma..-rays (photons) from an external source Compton scattered from the tissue under inspection. The method provides chemical information of plane regions lying not too deep inside the body (<6 cm). The amount of radiation absorbed by the body is about the same as needed for a standard x-r… more
Date: February 27, 1986
Creator: Gatti, E.; Rehak, P. & Kemmer, J.
Partner: UNT Libraries Government Documents Department
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Type B investigation report of curium-244 exposure at the ORNL TRU Facility, January 15, 1986

Description: This Type B Investigative Report provides an evaluation of relevant events and activities that led to, were a part of, or resulted from the release of curium-244 in the Building 7920 facility at ORNL in January 1986. Impacts have been evaluated with respect to employee exposures and the costs and loss of productivity resulting from increased bioassay analyses and activities of investigative committees. Management systems evaluated include (1) training of employees performing lab analyses, (2) a… more
Date: April 1, 1986
Creator: Love, G. L.; Butler, H. M.; Duncan, D. T. & Oakes, T. W.
Partner: UNT Libraries Government Documents Department
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Safety analysis of the existing 850 Firing Facility

Description: A safety analysis was performed to determine if normal operations and/or potential accidents at the 850 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitud… more
Date: June 5, 1986
Creator: Odell, B.N.
Partner: UNT Libraries Government Documents Department
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RTNS-II: experience at 14-MeV source strengths between 1 x 10/sup 13/ and 4 x 10/sup 13/ n/s

Description: The design concepts, operational experience, and modifications of the two RTNS-II (Rotating Target Neutron Source-II) 14 MeV neutron sources are reviewed. The original design called for operation at a peak neutron source strength of 4 x 10/sup 13/ n/cm/sup 2/s. The facility was to operate at high plant factor and at an acceptable cost in both dose delivered to operating staff and releases to the environment. The possibilities of higher source strengths are discussed in light of the operating ex… more
Date: May 1, 1986
Creator: Davis, J. C.
Partner: UNT Libraries Government Documents Department
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Offsite radiation doses summarized from Hanford environmental monitoring reports for the years 1957-1984. [Contains glossary]

Description: Since 1957, evaluations of offsite impacts from each year of operation have been summarized in publicly available, annual environmental reports. These evaluations included estimates of potential radiation exposure to members of the public, either in terms of percentages of the then permissible limits or in terms of radiation dose. The estimated potential radiation doses to maximally exposed individuals from each year of Hanford operations are summarized in a series of tables and figures. The ap… more
Date: February 1, 1986
Creator: Soldat, J. K.; Price, K. R. & McCormack, W. D.
Partner: UNT Libraries Government Documents Department
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Description and application of the AERIN Code at LLNL

Description: The AERIN code was written at the Lawrence Livermore National Laboratory in 1976 to compute the organ burdens and absorbed dose resulting from a chronic or acute inhalation of transuranic isotopes. The code was revised in 1982 to reflect the concepts of ICRP-30. This paper will describe the AERIN code and how it has been used at LLNL to study more than 80 cases of internal deposition and obtain estimates of internal dose. A comparison with the computed values of the committed organ dose is made… more
Date: January 2, 1986
Creator: King, W.C.
Partner: UNT Libraries Government Documents Department
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Risk equivalent of exposure versus dose of radiation

Description: This report describes a risk analysis study of low-dose irradiation and the resulting biological effects on a cell. The author describes fundamental differences between the effects of high-level exposure (HLE) and low-level exposure (LLE). He stresses that the concept of absorbed dose to an organ is not a dose but a level of effect produced by a particular number of particles. He discusses the confusion between a linear-proportional representation of dose limits and a threshold-curvilinear repr… more
Date: January 1, 1986
Creator: Bond, V.P.
Partner: UNT Libraries Government Documents Department
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Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

Description: This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to expo… more
Date: January 1, 1986
Creator: Elder, J. C.; Graf, J. M.; Dewart, J. M.; Buhl, T. E.; Wenzel, W. J.; Walker, L. J. et al.
Partner: UNT Libraries Government Documents Department
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Cost-effectiveness studies as part of an ALARA program

Description: Recent studies of cost effectiveness of engineering modifications for dose reduction at nuclear power plants conducted at BNL will be considered in this report. Since each of these items has the potential for a 50% to 60% reduction in collective dose, it appears there is large potential for dose reduction from engineering type modifications. The question that must be answered for each plant is ''which modifications or improvements are required for optimization (ALARA). The purpose of this paper… more
Date: January 1, 1986
Creator: Baum, J.W.
Partner: UNT Libraries Government Documents Department
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Research and development activities on Three Mile Island Unit Two. Annual report for 1985

Description: The year 1985 was significant in the cleanup of Three Mile Island Unit 2 (TMI-2). Major milestones in the project included lifting the plenum assembly from the reactor vessel and the start of operations to remove the damaged fuel from the reactor. This report summarizes these milestones and other TMI-2 related cleanup, research, and development activities. Other major topics include the following: waste immobilization and management; fuel shipping cask delivery and testing; sample acquisition a… more
Date: April 1, 1986
Partner: UNT Libraries Government Documents Department
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