V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009
Description
V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)
Files
42070638.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 168 p.
- ISSN
- 0944-2952
- Report number
- Juel--4326
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42070638
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Computer Program Description
- Descriptors DEI
- BURNUP; COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; CROSS SECTIONS; E CODES; FUEL CYCLE; FUEL ELEMENTS; GAS COOLED REACTORS; NUMERICAL SOLUTION; REACTOR FUELING; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL SOLUTIONS; MECHANICS; REACTOR COMPONENTS; REACTORS; SIMULATION
Optional Information
- Notes
- 30 refs.