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Reactor Shielding Design Manual

Description: The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date: March 1956
Creator: Rockwell, Theodore, III
Partner: UNT Libraries Government Documents Department

Partial Return Yoke for MICE

Description: The international Muon Ionization Cooling Experiment (MICE) is a large scale experiment which is presently assembled at the Rutherford Appleton Laboratory in Didcot, UK. The purpose of MICE is to demonstrate the concept of ionization cooling experimentally. Ionization cooling is an important accelerator concept which will be essential for future HEP experiments such as a potential Muon Collider or a Neutrino Factory. The MICE experiment will house up to 18 superconducting solenoids, all of which produce a substantial amount of magnetic flux. Recently it was realized that this magnetic flux leads to a considerable stray magnetic field in the MICE hall. This is a concern as technical equipment in the MICE hall may may be compromised by this. In July 2012 a concept called partial return yoke was presented to the MICE community, which reduces the stray field in the MICE hall to a safe level. This report summarizes the general concept, engineering considerations and the expected shielding performance.
Date: May 3, 2013
Creator: Witte, Holger & Plate, Stephen
Partner: UNT Libraries Government Documents Department

A Problem in the Conversion of Neutron Dose to Flux

Description: This report discusses the calculation involved in converting neutron dose to flux. In order to test conversion calculation methods, the flux entering the Oak Ridge National Laboratory Lid Tank and the water by the north face of the Oak Ridge National Laboratory Bulk Shielding Reactor was used.
Date: June 29, 1953
Creator: McMillan, D. E.
Partner: UNT Libraries Government Documents Department

Field Handling Study of Heavy Aggregate Concrete

Description: Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""
Date: December 7, 1951
Creator: Emmons, C. D.
Partner: UNT Libraries Government Documents Department

Optimization of next-event estimation probability in Monte Carlo shielding calculations

Description: In Monte Carlo radiation transport calculations with point detectors, the next-event estimation is employed to estimate the response to each detector from all collision sites. The computation time required for this estimation process is substantial and often exceeds the time required to generate and process particle histories in a calculation. This estimation from all collision sites is, therefore, very wasteful in Monte Carlo shielding calculations. For example, in the source region and in regions far away from the detectors, the next-event contribution of a particle is often very small and insignificant. A method for reducing this inefficiency is described. (WHK)
Date: January 1, 1983
Creator: Hoffman, T.J. & Tang, J.S.
Partner: UNT Libraries Government Documents Department

RSIC after 14 years: where do we go from here. [Brief history and list of suggested future activities]

Description: During the fourteen years since the Radiation Shielding Information Center (RSIC) started operations, many changes have taken place in the nuclear industry, both government and commercial, and in shielding technology. Military and space applications of radiation transport technology have waxed and waned, but computing applications and the need for elaborate computer codes and nuclear data for the commercial nuclear industry have increased manyfold. The rationale for RSIC operations has been the recognition of the need for government to promote the exchange and transfer of shielding technology to advance the state of the art. With the present need to meet energy demands through nuclear power, and yet to minimize radiation exposure to operating personnel and the public, there is great need to increase radiation analysis capabilities among the utilities and other segments of the industry. Yet, because of government cost-recovery restrictions and Electric Power Research Institute (EPRI) precedents, there is a widening gap between what is being done and what is needed. During 1975, RSIC had an Electric Power Research Institute contract to integrate the shielding and technology information exchange of the nuclear power industry with that of the government and its contractors. Included in work performed by RSIC on behalf of EPRI was a survey of the radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Such needs include computing technology, nuclear data, special information needs, such as fission product and ''crud'' transport, and expansion more generally into radiation protection areas such as environmental radiological analysis.
Date: January 1, 1977
Creator: Trubey, D. K.; Maskewitz, B. F. & Roussin, R. W.
Partner: UNT Libraries Government Documents Department

Shielding of External Magnetic Perturbations By Torque In Rotating Tokamak Plasmas

Description: The imposition of a nonaxisymmetric magnetic perturbation on a rotating tokamak plasma requires energy and toroidal torque. Fundamental electrodynamics implies that the torque is essentially limited and must be consistent with the external response of a plasma equilibrium ƒ = j x B. Here magnetic measurements on National Spherical Torus eXperiment (NSTX) device are used to derive the energy and the torque, and these empirical evaluations are compared with theoretical calculations based on perturbed scalar pressure equilibria ƒ = ∇p coupled with the theory of nonambipolar transport. The measurement and the theory are consistent within acceptable uncertainties, but can be largely inconsistent when the torque is comparable to the energy. This is expected since the currents associated with the torque are ignored in scalar pressure equilibria, but these currents tend to shield the perturbation.
Date: August 24, 2009
Creator: Jong-Kyu Park, Allen H. Boozer, Jonathan E. Menard, Stefan P. Gerhardt, and Steve A. Sabbagh
Partner: UNT Libraries Government Documents Department

Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department

Preliminary shielding estimates for the proposed National ISOL Radioactive Ion Beam (RIB) Facility at Oak Ridge

Description: ORNL built a first-generation Radioactive Ion Beam (RIB) facility for astrophysics and nuclear physics research; it was named Holifield Radioactive Ion Beam Facility (HRIBF) and is based on the Isotope Separator On Line (ISOL) technique. Planning is underway for a second- generation facility, the National ISOL RIB facility at Oak Ridge; it will build on the existing HRIBF and may utilize many existing components and shielded areas. Preliminary upgrade plan for the new facility includes: adding a superconducting booster for the tandem accelerator; replacing the 1960-vintage, 60-MeV proton, 50-microamp ORIC (Oak Ridge Isochronous Cyclotron) with a modern 200-MeV proton, 200-microamp cyclotron; and building a high-power {sup 238}U fission target to accept the 200-MeV proton beam. This report summarizes the results of a preliminary 1-D shielding analysis of the proposed upgrade, to determine the shielding requirements for a 0.25 mrem/h dose rate at the external surface of the exclusion area. Steel shielding weights ranging from 60 to 100 metric tons, were considered manageable; these could be reduced by a factor of 2 to 3 if the orientation of the proposed target station was changed.
Date: October 1, 1996
Creator: Johnson, J.O.; Gabriel, T.A. & Lillie, R.A.
Partner: UNT Libraries Government Documents Department

Beam collimation and shielding in the Fermilab proton driver

Description: A high beam power in the proposed Fermilab Proton Drivers--1.2 MW in 16-GeV PD-I and 0.48 MW in 8-GeV PD-II--implies serious constraints on beam losses in these machines. Only with a very efficient beam collimation system can one reduce uncontrolled beam losses in the machine to an allowable level. The entire complex must be well shielded to allow acceptable hands-on maintenance conditions in the tunnel and a non-controlled access to the outside shielding at normal operation and accidental beam loss. Collimation and shielding performances are calculated and compared for both Proton Drivers.
Date: June 28, 2002
Creator: Mokhov, Alexandr I. Drozhdin and Nikolai V.
Partner: UNT Libraries Government Documents Department

Self-Shielding Measurements in PPA-20

Description: From Introduction: "The self-shielding characteristics of a number of absorbers and of U-235 and U-238 have been investigated in PPA-20 (66°). Most of the measurements have been made in Ring 3 at the core mid-plane. The foil doubling technique was employed. Particular attention was given to 'thin' foil regions for the purpose of extrapolating the data to zero thickness."
Date: September 9, 1954
Creator: King, J. S.
Partner: UNT Libraries Government Documents Department

Measurements of an Iron and Borated Water Shield in the Lid Tank : Experiment 10

Description: The following report measures a shield mockup in three regions: the first made almost entire of iron; the second, transition, region is made of various thicknesses of B4C; and the third region was borated water. The iron samples used in the experiments were made in the form of rectangular plates and place in the lid tank; however, the plates were not completely flat and created a water gap that was measured in this report.
Date: December 14, 1950
Creator: Blizard, E. P. & Clifford, C. E.
Partner: UNT Libraries Government Documents Department

Radiation Shielding for Test Cell "C"

Description: "This report contains information on the following topics related to the radiation shielding at test cell "C". (1) Calculation of wall and roof thicknesses. (2) Calculation of radiation heating of front wall by gamma and neutron absorption. (3) Calculation of neutron activation in front face of test cell. (4) Calculation of γ-dose rates both direct and behind shadow shields at various distances. (5) Dose produced by a reactor catastrophe."
Date: June 1959
Creator: Fenstermacher, Charles Alvin & Henshall, James
Partner: UNT Libraries Government Documents Department