Actions for Argonne Code Center [electronic resource] : benchmark problem book
Argonne Code Center [electronic resource] : benchmark problem book
- Published
- La Grange Park, Ill. : American Nuclear Society, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 369 : digital, PDF file
- Additional Creators
- American Nuclear Society and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- This report is a supplement to the original report, published in 1968, as revised. The Benchmark Problem Book is intended to serve as a source book of solutions to mathematically well-defined problems for which either analytical or very accurate approximate solutions are known. This supplement contains problems in eight new areas: two-dimensional (R-z) reactor model; multidimensional (Hex-z) HTGR model; PWR thermal hydraulics--flow between two channels with different heat fluxes; multidimensional (x-y-z) LWR model; neutron transport in a cylindrical ''black'' rod; neutron transport in a BWR rod bundle; multidimensional (x-y-z) BWR model; and neutronic depletion benchmark problems. This supplement contains only the additional pages and those requiring modification. (RWR)
- Report Numbers
- E 1.99:anl-7416(suppl.2)
anl-7416(suppl.2) - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Neutron Transport
- Fuel Rods
- Htgr Type Reactors
- Standards
- Pwr Type Reactors
- Hydraulics
- Neutron Flux
- Fluid Mechanics
- Fuel Elements
- Gas Cooled Reactors
- Graphite Moderated Reactors
- Mechanics
- Neutral-Particle Transport
- Radiation Flux
- Radiation Transport
- Reactor Components
- Reactors
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
06/01/1977.
"anl-7416(suppl.2)" - Funding Information
- W-31-109-ENG-38
View MARC record | catkey: 14673036