Micklich, B. J.; Iverson, E. B.; Carpenter, J. M.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
AbstractAbstract
[en] The Spallation Neutron Source (SNS), under construction at Oak Ridge National Laboratory, will be the premier facility for neutron scattering studies in the United States. From the outset the SNS can achieve additional flexibility and accommodate a broader range of scientific investigation than would be possible with only the High Power Target Station by utilizing two target stations, each operating under a separate set of conditions and optimized for a certain class of instruments. A second target station, termed the Long-Wavelength Target Station (LWTS), would operate at a lower pulse rate (e.g., 10 vs. 60 Hz) and utilize very cold moderators to emphasize low-energy (long wavelength) neutrons. The LWTS concept discussed here obtains the highest low-energy fluxes possible for neutron scattering instruments by using a heavy-water-cooled solid tungsten target with two moderators in slab geometry and one in a front wing position. The primary focus has been on solid methane moderators, with liquid methane and hydrogen also considered. We used MCNPX to conduct a series of optimization and sensitivity studies to help determine the optimal neutronic parameters of the LWTS. We compared different options based on the thermal and epithermal fluxes as determined by fitting the spectral intensity of the moderators with a Maxwellian peak and a modified Westcott function. The primary parameters are the moderator positions and composition and the target size. We report results for spectral intensity, pulse shapes, high-energy neutron emission, heating profiles in the target, and target activation
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21 Sep 2001; 10 p; W-31-109-ENG-38; Available from Argonne National Lab., IL (US)
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Micklich, B. J.; Smith, D. L.; Massey, T. N.; Ingram, D.; Fessler, A.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2000
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2000
AbstractAbstract
[en] Potential diversion of nuclear materials is a major international concern. Fissile (e.g., U, Pu) and other nuclear materials (e.g., D, Be) can be detected using 6-7 MeV gamma rays produced in the 19F(p,αγ)16O reaction. These gamma rays will induce neutron emission via the photoneutron and photofission processes in nuclear materials. However, they are not energetic enough to generate significant numbers of neutrons from most common benign materials, thereby reducing the false alarm rate. Neutrons are counted using an array of BF3 counters in a polyethylene moderator. Experiments have shown a strong increase in neutron count rates for depleted uranium, Be, D2O, and 6Li, and little or no increase for other materials (e.g., H2O, SS, Cu, Al, C, 7Li). Gamma source measurements using solid targets of CaF2 and MgF2 and a SF6 gas target show that proton accelerator of 3 MeV and 10-100 microampere average current could lead to acceptable detection sensitivity
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10 Oct 2000; 6 p; 16. International Conference on the Application of Accelerators in Research and Industry, CAARI 2000; Denton, TX (United States); 1-4 Nov 2000; W-31-109-ENG-38; Also available from OSTI as DE00766332; PURL: https://www.osti.gov/servlets/purl/766332-DOrsvW/webviewable/
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Micklich, B. J.; Smith, D. L.; Massey, T. N.; Fink, C. L.; Ingram, D.; Technology Development; Ohio Univ.
Argonne National Laboratory ANL (United States). Funding organisation: LDRD (US)2003
Argonne National Laboratory ANL (United States). Funding organisation: LDRD (US)2003
AbstractAbstract
[en] We measured the photon yields for proton energies between 1.5 and 4.25 MeV using both CaF2 and MgF2 solid targets and SF6 gas targets. Photon yields were measured using a 7.62 cm x 7.62 cm NaI scintillator detector. Detector response functions for these three individual γ-rays were calculated using the Monte Carlo code MCNP-4C. The relative intensities of the three γ-rays were determined by a least-squares fit of these response functions to the data in a selected region of the pulse-height spectrum. A maximum photon yield of 6.0x107 γ/(micro)C/sr (at 0 degrees) was determined for the sum of these three γ-rays at an effective proton energy of 4.0 MeV. The contribution of the individual lines to the total photon yield depends strongly on the incident proton energy
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1 Jun 2003; 3 p; 10. Symposium on Radiation Measurements and Applications; Ann Arbor, MI (United States); 21-23 May 2002; AC02-06CH11357; Available from Nucl. Instrum. Methods Phys. Res. A; doi 10.1016/S0168-9002(03)01006-4
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Micklich, B. J.; Gallmeier, F. X.; Iverson, E. B.; Lu, W.; Popova, I.; Wolhmuther, M.; Holloway, S. T.; Kelsey, C. T.; Mocko, M.; Wilson, W. B.
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)2014
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)2014
AbstractAbstract
[en] CINDER is a transmutation code, developed originally at the Bettis Atomic Power Laboratory, which predicts induced radioactivity due to either reactor or accelerator-driven radiation sources. The code and associated data libraries have been expanded and improved over the years at Los Alamos National Laboratory. CINDER08 is the latest update in the series and represents a complete rewrite of CINDER, improving it in many areas. Beginning with CINDER90, several Perl scripts were developed to treat multi-cell problems in combination with the radiation transport code MCNPX. These scripts simplified the preparation of CINDER input and made the code much more user-friendly. In concert with the development of CINDER08, these scripting tools have also been updated. The script developers are intensive users of CINDER and had significant input into the development of CINDER08. CINDER08, through use of these scripts, also works with output from MCNP5, which is useful for problems that do not require the extended particle capabilities of MCNPX and do not require particle energies outside of the tabular physics regime, and with MCNP6. A new version of CINDER, CINDER08, incorporates many improvements to the coding and the data libraries. Updated versions of scripting tools improve the code's usability and simplify the use of CINDER output as the basis of gamma source terms for subsequent calculations. (authors)
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Sep 2014; 4 p; American Nuclear Society - ANS; La Grange Park, IL (United States); RPSD 2014: 18. Topical Meeting of the Radiation Protection and Shielding Division of ANS; Knoxville, TN (United States); 14-18 Sep 2014; ISBN 978-0-89448-714-9; ; Country of input: France; 11 refs.; available on CD Rom from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
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