Studies of axial-leakage simulations for homogeneous and heterogeneous EBR-II core configurations [electronic resource]
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross se...
Saved in:
| Online Access: |
Online Access |
|---|---|
| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Argonne, Ill. : Oak Ridge, Tenn. :
Argonne National Lab ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1985.
|
| Subjects: |
MARC
| LEADER | 00000nam a22000003u 4500 | ||
|---|---|---|---|
| 001 | b6007881 | ||
| 003 | CoU | ||
| 005 | 20080822000000.0 | ||
| 006 | m d f | ||
| 007 | cr un | ||
| 008 | 100527e19850801ilu st f0|||||eng|d | ||
| 035 | |a (TOE)ost5148077 | ||
| 035 | |a (TOE)5148077 | ||
| 040 | |a TOE |c TOE | ||
| 049 | |a GDWR | ||
| 072 | 7 | |a 21 |2 edbsc | |
| 086 | 0 | |a E 1.99:anl-85-28 | |
| 086 | 0 | |a E 1.99:anl-85-28 | |
| 245 | 0 | 0 | |a Studies of axial-leakage simulations for homogeneous and heterogeneous EBR-II core configurations |h [electronic resource] |
| 260 | |a Argonne, Ill. : |b Argonne National Lab ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1985. | ||
| 300 | |a Pages: 71 : |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 the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 08/01/1985. | ||
| 500 | |a "anl-85-28" | ||
| 500 | |a "DE86001305" | ||
| 500 | |a Grimm, K.N.; Meneghetti, D. | ||
| 520 | 3 | |a When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross sections, are also axially dependent. Therefore, to obtain axial flux profiles (or reaction rates) for individual subassemblies, an XY-geometry calculation delineating each subassembly has to be done at several axial heights with space- and energy-dependent leakage-absorption cross sections that are appropriate for each height. This report discusses homogeneous and heterogeneous XY-geometry calculations at various axial locations and using several differing assumptions for the calculation of the leakage-absorption cross section. The positive (outward) leakage-absorption cross sections are modeled as actual leakage absorptions, but the negative (inward) leakage-absorption cross sections are modeled as either negative leakage absorptions (+-B² method) or positive downscatter cross sections (the ..sigma../sub s/(1 ..-->.. g) method). 3 refs., 52 figs., 10 tabs. | |
| 536 | |b W-31-109-ENG-38. | ||
| 650 | 7 | |a Beta Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Ebr-2 Reactor. |2 local. | |
| 650 | 7 | |a Heavy Nuclei. |2 local. | |
| 650 | 7 | |a Tantalum Isotopes. |2 local. | |
| 650 | 7 | |a Experimental Reactors. |2 local. | |
| 650 | 7 | |a Mathematical Models. |2 local. | |
| 650 | 7 | |a Xenon Isotopes. |2 local. | |
| 650 | 7 | |a Xenon 135. |2 local. | |
| 650 | 7 | |a Tantalum 181. |2 local. | |
| 650 | 7 | |a Beta-minus Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Liquid Metal Cooled Reactors. |2 local. | |
| 650 | 7 | |a Lmfbr Type Reactors. |2 local. | |
| 650 | 7 | |a Even-even Nuclei. |2 local. | |
| 650 | 7 | |a Research And Test Reactors. |2 local. | |
| 650 | 7 | |a Actinide Isotopes. |2 local. | |
| 650 | 7 | |a Even-odd Nuclei. |2 local. | |
| 650 | 7 | |a Stable Isotopes. |2 local. | |
| 650 | 7 | |a Sodium Cooled Reactors. |2 local. | |
| 650 | 7 | |a Isotopes. |2 local. | |
| 650 | 7 | |a Power Reactors. |2 local. | |
| 650 | 7 | |a Boron Isotopes. |2 local. | |
| 650 | 7 | |a Reactor Cores. |2 local. | |
| 650 | 7 | |a Uranium Isotopes. |2 local. | |
| 650 | 7 | |a Uranium 238. |2 local. | |
| 650 | 7 | |a Intermediate Mass Nuclei. |2 local. | |
| 650 | 7 | |a Breeder Reactors. |2 local. | |
| 650 | 7 | |a Isomeric Transition Isotopes. |2 local. | |
| 650 | 7 | |a Computer Calculations. |2 local. | |
| 650 | 7 | |a Epithermal Reactors. |2 local. | |
| 650 | 7 | |a Odd-even Nuclei. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Odd-odd Nuclei. |2 local. | |
| 650 | 7 | |a Minutes Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Neutron Flux. |2 local. | |
| 650 | 7 | |a Actinide Nuclei. |2 local. | |
| 650 | 7 | |a Fbr Type Reactors. |2 local. | |
| 650 | 7 | |a Fast Reactors. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Radiation Flux. |2 local. | |
| 650 | 7 | |a Light Nuclei. |2 local. | |
| 650 | 7 | |a Alpha Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Boron 10. |2 local. | |
| 650 | 7 | |a Nuclei. |2 local. | |
| 650 | 7 | |a Years Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Radioisotopes. |2 local. | |
| 650 | 7 | |a Hours Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Argonne National Laboratory. |4 res. | |
| 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/servlets/purl/5148077-IJkDVV/ |z Online Access |
| 907 | |a .b60078819 |b 03-06-23 |c 05-30-10 | ||
| 998 | |a web |b 05-30-10 |c f |d m |e p |f eng |g ilu |h 0 |i 1 | ||
| 956 | |a Information bridge | ||
| 999 | f | f | |i ffde4840-e25c-511f-a29e-801efa71c625 |s 784e22ae-5c83-5f81-9aff-25b23e1adaab |
| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:anl-85-28 |h Superintendent of Documents classification |i web |n 1 |