Development of improved methods for the LWR lattice physics code EPRI-CELL [electronic resource]
A number of improvements have been made by ORNL to the lattice physics code EPRI-CELL (E-C) which is widely used by utilities for analysis of power reactors. The code modifications were made mainly in the thermal and epithermal routines and resulted in improved reactor physics approximations and mor...
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Online Access (via OSTI) |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1982.
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| Subjects: |
MARC
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| 088 | |a ornl/tm-8411 | ||
| 245 | 0 | 0 | |a Development of improved methods for the LWR lattice physics code EPRI-CELL |h [electronic resource] |
| 260 | |a Oak Ridge, Tenn. : |b Oak Ridge National Laboratory. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1982. | ||
| 300 | |a Pages: 60 : |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 07/01/1982. | ||
| 500 | |a "ornl/tm-8411" | ||
| 500 | |a "DE82018579" | ||
| 500 | |a Williams, M.L.; Wright, R.Q.; Barhen, J. | ||
| 520 | 3 | |a A number of improvements have been made by ORNL to the lattice physics code EPRI-CELL (E-C) which is widely used by utilities for analysis of power reactors. The code modifications were made mainly in the thermal and epithermal routines and resulted in improved reactor physics approximations and more efficient running times. The improvements in the thermal flux calculation included implementation of a group-dependent rebalance procedure to accelerate the iterative process and a more rigorous calculation of interval-to-interval collision probabilities. The epithermal resonance shielding methods used in the code have been extensively studied to determine its major approximations and to examine the sensitivity of computed results to these approximations. The study has resulted in several improvements in the original methodology. | |
| 536 | |b W-7405-ENG-26. | ||
| 650 | 7 | |a Bwr Type Reactors. |2 local. | |
| 650 | 7 | |a Reactor Kinetics. |2 local. | |
| 650 | 7 | |a Cross Sections. |2 local. | |
| 650 | 7 | |a Computer Calculations. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Fuel Pins. |2 local. | |
| 650 | 7 | |a Monte Carlo Method. |2 local. | |
| 650 | 7 | |a Reactor Cores. |2 local. | |
| 650 | 7 | |a Uranium Dioxide. |2 local. | |
| 650 | 7 | |a Actinide Compounds. |2 local. | |
| 650 | 7 | |a Chalcogenides. |2 local. | |
| 650 | 7 | |a Fuel Elements. |2 local. | |
| 650 | 7 | |a Kinetics. |2 local. | |
| 650 | 7 | |a Oxides. |2 local. | |
| 650 | 7 | |a Oxygen Compounds. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Uranium Compounds. |2 local. | |
| 650 | 7 | |a Uranium Oxides. |2 local. | |
| 650 | 7 | |a Water Cooled Reactors. |2 local. | |
| 650 | 7 | |a Water Moderated Reactors. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Oak Ridge 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/scitech/biblio/5334088 |z Online Access (via OSTI) |
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