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140801e19780101||| o| f1|||||eng|d |
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|a (TOE)ost6804135
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|a (TOE)6804135
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|a TOE
|c TOE
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:conf-780401--7
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|a E 1.99:conf-780401--7
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| 088 |
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|a conf-780401--7
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| 245 |
0 |
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|a Neutronics analysis of the low proliferating gas core reactor
|h [electronic resource]
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| 260 |
|
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|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 1978.
|
| 300 |
|
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|a Pages: 14 :
|b digital, PDF file.
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| 336 |
|
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|a text
|b txt
|2 rdacontent.
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| 337 |
|
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|a computer
|b c
|2 rdamedia.
|
| 338 |
|
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through SciTech Connect.
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| 500 |
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|a 01/01/1978.
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| 500 |
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|a "conf-780401--7"
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| 500 |
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|a Topical meeting on advances in reactor physics, Gatlinburg, TN, USA, 9 Apr 1978.
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| 500 |
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|a Wessol, D. E.; Olson, W. O.; Close, J. A.
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| 500 |
|
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|a Idaho National Engineering Lab., Idaho Falls (USA)
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| 520 |
3 |
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|a The recent interest in the development of proliferation resistant fuel cycles has prompted an investigation of the gas core reactor concept. The gas core reactor consists of a cavity containing fissile material in a gaseous state surrounded by an external reflector-moderator. A fuel-coolant mixture of UF/sub 6/ and Helium is considered in most gas-core reactor conceptual designs. Currently this concept is one of several being considered for the Non-proliferation Alternate Systems Assessment Program (NASAP). Since the gas core reactor is seen to present special difficulties with respect to reactor physics analysis, the INEL gas core critical benchmark offered an ideal test of reactor physics methods. The experiment was analyzed with Monte Carlo, S/sub n/ transport theory and diffusion theory methods. Diffusion theory methods are shown to be inadequate for the gas core concept. More importantly, it is shown that a high order scattering approximation is necessary to accurately predict experimental results, regardless of method. Convergence was found to be particularly sensitive to the selection of acceleration strategies and parameters.
|
| 536 |
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|b EY-76-C-06-1570.
|
| 650 |
|
7 |
|a Gas Fueled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactor Kinetics.
|2 local.
|
| 650 |
|
7 |
|a Neutron Transport.
|2 local.
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| 650 |
|
7 |
|a Uranium Hexafluoride.
|2 local.
|
| 650 |
|
7 |
|a Actinide Compounds.
|2 local.
|
| 650 |
|
7 |
|a Fluid Fueled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Fluorides.
|2 local.
|
| 650 |
|
7 |
|a Fluorine Compounds.
|2 local.
|
| 650 |
|
7 |
|a Halides.
|2 local.
|
| 650 |
|
7 |
|a Halogen Compounds.
|2 local.
|
| 650 |
|
7 |
|a Homogeneous Reactors.
|2 local.
|
| 650 |
|
7 |
|a Kinetics.
|2 local.
|
| 650 |
|
7 |
|a Radiation Transport.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Uranium Compounds.
|2 local.
|
| 650 |
|
7 |
|a Neutral-Particle Transport.
|2 local.
|
| 650 |
|
7 |
|a Uranium Fluorides.
|2 local.
|
| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|4 spn.
|
| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/6804135/
|z Online Access
|
| 907 |
|
|
|a .b72125949
|b 03-07-23
|c 11-08-12
|
| 998 |
|
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|a web
|b 11-08-12
|c f
|d b
|e p
|f eng
|g
|h 0
|i 2
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
f |
|i 9481cc40-5ef4-5049-93eb-867cae1d3f2c
|s 5af83ace-471d-5bb7-b700-183308d3e80a
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-780401--7
|h Superintendent of Documents classification
|i web
|n 1
|
