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130211e19981201dcu ot f0|||||eng|d |
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|a (TOE)ost2690
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|a (TOE)2690
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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:ornl/sub/98-85b99398v-1
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|a E 1.99:ornl/sub/98-85b99398v-1
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| 088 |
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|a ornl/sub/98-85b99398v-1
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| 245 |
0 |
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|a Results of Parametric Design Studies of MOX Lead Test Assembly
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Energy. Office of Fissile Materials Disposition ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1998.
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| 300 |
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|a 99 pages :
|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.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 12/01/1998.
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| 500 |
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|a "ornl/sub/98-85b99398v-1"
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| 500 |
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|a Bychkov, S.A.; Pavlovitchev, A.M.; Lazarenko, A.A.; Sidorenko, V.D.; Styrin, Y.A.
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| 513 |
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|a Topical;
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| 520 |
3 |
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|a The parametric studies of MOX LTA design have been executed to choose plutonium content in assembly zones for two options of MOX LTA: 3-zones and Island. For 3-zones (100% Plutonium) MOX LTA the fissile plutonium content composition of 4.2%/3,0%/2% has been chosen. MOX LTA of the chosen compositions has been studied by using multi-assembly configuration that allows investigating of influence of MOX LTA environment: uranium assemblies of different irradiation. Plutonium Island with 54 plutonium pins in the center of MOX LTA has been considered in two modifications: uniform island; and graded island with lower plutonium content in one peripheral row of pins. It is shown that plutonium content in the uniform island cannot exceed 2.7% because of adopted power peaking limitations and therefore this design seems unreasonable for practical use. For graded island the plutonium content composition 3.8%/2.8% with uranium environment of 3.7% U-235 has been chosen. Evolution of assembly power and burnup distributions, inter-pin power and isotopic distributions while fuel irradiating have been analyzed. In addition to the base uranium environment of 3.7%, a set of calculations has been executed for 4.4%. Most of the studies have been executed by the code TVS-M that is at the final stage of licensing and it is to be used in the nearest future as a base instrument for VVER core calculations while using both uranium and MOX fuel. So the obtained results must be considered as preliminary ones and they demand additional analysis and investigations.
|
| 536 |
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|b AC05-96OR22464.
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| 650 |
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7 |
|a Design.
|2 local.
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| 650 |
|
7 |
|a Wwer Type Reactors.
|2 local.
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| 650 |
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7 |
|a Uranium.
|2 local.
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| 650 |
|
7 |
|a Licensing.
|2 local.
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| 650 |
|
7 |
|a Concentration Ratio.
|2 local.
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| 650 |
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7 |
|a Mixed Oxide Fuels.
|2 local.
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| 650 |
|
7 |
|a Parametric Analysis.
|2 local.
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| 650 |
|
7 |
|a Reactor Kinetics.
|2 local.
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| 650 |
|
7 |
|a Fuel Assemblies.
|2 local.
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| 650 |
|
7 |
|a Burnup.
|2 local.
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| 650 |
|
7 |
|a Plutonium.
|2 local.
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| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
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| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
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|a Oak Ridge National Laboratory.
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Fissile Materials Disposition.
|4 spn.
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| 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/2690/
|z Online Access
|
| 907 |
|
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|a .b73152420
|b 03-07-23
|c 02-11-13
|
| 998 |
|
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|a web
|b 02-11-13
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 2
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
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|i dac2341c-eade-5105-843e-f32afed9c036
|s 59c7fe08-4622-5984-a426-0b12b5422e1c
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/sub/98-85b99398v-1
|h Superintendent of Documents classification
|i web
|n 1
|
