313 research outputs found
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The CALOR93 code system
The purpose of this paper is to describe a program package, CALOR93, that has been developed to design and analyze different detector systems, in particular, calorimeters which are used in high energy physics experiments to determine the energy of particles. One`s ability to design a calorimeter to perform a certain task can have a strong influence upon the validity of experimental results. The validity of the results obtained with CALOR93 has been verified many times by comparison with experimental data. The codes (HETC93, SPECT93, LIGHT, EGS4, MORSE, and MICAP) are quite generalized and detailed enough so that any experimental calorimeter setup can be studied. Due to this generalization, some software development is necessary because of the wide diversity of calorimeter designs
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CALOR as a Single Code Including a Modular Version of HETC
The major components of CALOR are HETC, MORSE, EGS4, EGS4PREP, and SPECT, working sequentially on calorimeter detector for high energy physics, experimental analysis, or shielding studies. An effort to combine the components into a single code is described. The new code is modular in nature. For example, one may run only HETC and MORSE. In addition, HETC itself has become modular and may be run in three energy options--up to 2.5 GeV, 15 GeV, and 20 TeV. The size of the low-energy option of HETC is less than 40% of the original HETC. A great advantage of the new code is the elimination of three huge files for passing information from one component to another
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The photoneutron yield predictions by PICA and comparison with the measurements
The photoneutron yields at higher photon energies have become very important since the advent of high energy electron accelerators. Bremsstrahlung is produced when the particle beam interacts with the storage-ring components or residual-gas molecules in the storage-ring vacuum. Bremsstrahlung thus produced interacts with the high-Z materials in the beamline like the beam dumps and collimators to produce photoneutrons. There are three modes of neutron production by bremsstrahlung. At low energies ({>=}525 MeV), photons are absorbed by the dipole interaction and the compound nucleus thus formed decays emitting protons and neutrons and other heavier particles. At higher energies ({>=}25 MeV), photon interacts with the nucleus through absorption on a quasi-deuteron, which subsequently decays producing a neutron and proton pair which can interact with the rest of the nucleus. At still higher energies the photopion production becomes possible and competes with the quasi-deuteron process. In this paper we have calculated the photoneutron yield from a thick copper target using the photonuclear interaction code PICA. Using this as the neutron source, we have calculated the dose rates through heavy concrete and compared it with the measurements made at the Advanced Photon Source at Argonne National Lab
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HETC96/MORSE calculations of activations in KEK beam stop and room by 500-MeV protons and comparisons with experiments
The 1996 version of HETC has a pre-equilibrium reaction model to bridge the gap between the existing intranuclear-cascade and evaporation models. This code was used to calculate proton-induced activations, to calculate neutron fluxes for neutron energies above 19.6 MeV, and to write the neutron source for lower energies to be transported further by MORSE. For MORSE, the HILO cross section library was used for neutron transport for all detectors. Additionally for the {sup 197}Au(n, {gamma}) detector, the BUGLE96 library was used to study the effects of the low-lying {sup 57}Fe inelastic levels and the resonance self-shielding in iron. Neutron fluxes were obtained from the track-length estimator for detectors inside the beam stop and from the boundary-crossing estimator for detectors attached to the surfaces of the concrete walls. Activation cross sections given in JAERI-Data/Code are combined with the calculated neutron fluxes to get the saturated activities induced by neutrons. C/E values are too low (0.5) for Fe(N, {chi}){sup 54}Mn, close to unity for Cu(n, {chi}){sup 58}Co, and too high (6.0) for {sup 197}Au (n, {gamma}){sup 198}Au. It is difficult to interpret the disagreements because most of the activation cross sections are also calculated and their uncertainties are not known. However, the calculated results are in good agreement with those calculated by others using different codes. Calculated results for four of the ten activations reported here have not been done previously, and among the four, {sup 197}Au(n, {gamma}) is the most bothersome because its cross section is the most well known while the calculated activations for most detector locations are in largest disagreement with experiments
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Overview of the national spallation neutron source with emphasis on the target station
The technologies that are being utilized to design and build a state-of-the-art neutron spallation source, the National Spallation Neutron Source (NSNS), are discussed. Emphasis is given to the technology issues that present the greatest scientific challenges. The present facility configuration, ongoing analysis and the planned hardware research and development program are also described
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The national spallation neutron source target station: A general overview
The technologies that are being utilized to design and build a state-of-the-art neutron spallation source, the National Spallation Neutron Source (NSNS), are discussed. Emphasis is given to the technology issues that present the greatest scientific challenges. The present facility configuration, ongoing analysis and the planned hardware research and development program are also described
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Preliminary shielding estimates for the proposed National ISOL Radioactive Ion Beam (RIB) Facility at Oak Ridge
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
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PICA95: An intranuclear-cascade code for 25-MeV to 3.5-GeV photon-induced nuclear reactions
PICA95, an intranuclear-cascade code for calculating photon-induced nuclear reactions for incident photon energies up to 3.5 GeV, is an extension of the original PICA code package that works for incident photon energies up to 400 MeV. The original code includes the quasi-deuteron breakup and single-pion production channels. The extension to an incident photon energy of 3.5 GeV requires the addition of multiple-pion production channels capable of emitting up to five pions. Relativistic phase-space relations are used to conserve energy and momentum in multi-body breakups. Fermi motion of the struck nucleon is included in the phase-space calculations as well as secondary nuclear collisions of the produced particles. Calculated doubly differential cross sections for the productions of protons, neutrons, {pi}{sup +}, {pi}{sup 0}, and {pi}{sup {minus}} for incident photon energies of 500 MeV, 1 GeV, and 2 GeV are compared with predictions by other codes. Due to the sparsity of experimental data, more experiments are needed in order to refine the gamma nuclear collision model
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Overview of the NSNS target station
The technologies that are being utilized to design and build a state-of-the-art neutron spallation source, the National Spallation Neutron Source (NSNS), are discussed. Emphasis is given to the technology issues that present the greatest scientific challenges. The present facility configuration, ongoing analysis and the planned hardware research and development program are also described
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