Monte carlo sampling of fission multiplicity. [electronic resource]
Fission Multiplicity; Monte Carlo; Gaussian Distribution; Radiation Transport.
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Online Access |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2004.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Monte carlo sampling of fission multiplicity. |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Department of Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2004. | ||
| 300 | |a [13] p. : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 01/01/2004. | ||
| 500 | |a "la-ur-04-6967" | ||
| 500 | |a Submitted to: Monte Carlo 2005 Topical Meeting, Chattanooga, Tennessee, April 17-25, 2005. | ||
| 500 | |a Hendricks, J. S. | ||
| 520 | 3 | |a Two new methods have been developed for fission multiplicity modeling in Monte Carlo calculations. The traditional method of sampling neutron multiplicity from fission is to sample the number of neutrons above or below the average. For example, if there are 2.7 neutrons per fission, three would be chosen 70% of the time and two would be chosen 30% of the time. For many applications, particularly ³He coincidence counting, a better estimate of the true number of neutrons per fission is required. Generally, this number is estimated by sampling a Gaussian distribution about the average. However, because the tail of the Gaussian distribution is negative and negative neutrons cannot be produced, a slight positive bias can be found in the average value. For criticality calculations, the result of rejecting the negative neutrons is an increase in k{sub eff} of 0.1% in some cases. For spontaneous fission, where the average number of neutrons emitted from fission is low, the error also can be unacceptably large. If the Gaussian width approaches the average number of fissions, 10% too many fission neutrons are produced by not treating the negative Gaussian tail adequately. The first method to treat the Gaussian tail is to determine a correction offset, which then is subtracted from all sampled values of the number of neutrons produced. This offset depends on the average value for any given fission at any energy and must be computed efficiently at each fission from the non-integrable error function. The second method is to determine a corrected zero point so that all neutrons sampled between zero and the corrected zero point are killed to compensate for the negative Gaussian tail bias. Again, the zero point must be computed efficiently at each fission. Both methods give excellent results with a negligible computing time penalty. It is now possible to include the full effects of fission multiplicity without the negative Gaussian tail bias. | |
| 520 | 0 | |a Fission Multiplicity; Monte Carlo; Gaussian Distribution; Radiation Transport. | |
| 650 | 7 | |a Criticality. |2 local. | |
| 650 | 7 | |a Distribution. |2 local. | |
| 650 | 7 | |a Fission. |2 local. | |
| 650 | 7 | |a Fission Neutrons. |2 local. | |
| 650 | 7 | |a Multiplicity. |2 local. | |
| 650 | 7 | |a Neutrons. |2 local. | |
| 650 | 7 | |a Radiation Transport. |2 local. | |
| 650 | 7 | |a Sampling. |2 local. | |
| 650 | 7 | |a Simulation. |2 local. | |
| 650 | 7 | |a Spontaneous Fission. |2 local. | |
| 650 | 7 | |a Physics Of Elementary Particles And Fields. |2 edbsc. | |
| 710 | 2 | |a Los Alamos National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/scitech/biblio/977889 |z Online Access |
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