New versions of VENTURE/PC, a multigroup, multidimensional diffusion-depletion code system
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7089785
- Univ. of Cincinnati, OH (United States)
VENTURE/PC is a microcomputer version of the BOLD VENTURE code system developed over a period of years at Oak Ridge National Laboratory (ORNL). It is a very complete and flexible multigroup, multidimensional, diffusion-depletion code system, which was developed for the Idaho National Engineering Laboratory personal computer (PC) based reactor physics and radiation shielding analysis package. The major characteristics of the code system were reported previously. Since that time, new versions of the code system have been developed. These new versions were designed to speed the convergence process, simplify the input stream, and extend the code to the state-of-the-art 32-bit microcomputers. The 16-bit version of the code is distributed by the Radiation Shielding Information Center (RSIC) at ORNL. The code has received widespread usage.
- OSTI ID:
- 7089785
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
Similar Records
Multidimensional multigroup diffusion-depletion calculations on the microcomputer
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system. Version 3
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5199890
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system. Version 3
Technical Report
·
Sat Nov 30 23:00:00 EST 1991
·
OSTI ID:10142142
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
Technical Report
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:5216999
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BURNUP
CALCULATION METHODS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CONVERGENCE
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
EDUCATION
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EQUATIONS
IDAHO NATIONAL ENGINEERING LABORATORY
ITERATIVE METHODS
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NATIONAL ORGANIZATIONS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
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PERSONAL COMPUTERS
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REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
SHIELDING
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
TRAINING
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
V CODES
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BURNUP
CALCULATION METHODS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CONVERGENCE
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
EDUCATION
EFFICIENCY
EQUATIONS
IDAHO NATIONAL ENGINEERING LABORATORY
ITERATIVE METHODS
MICROCOMPUTERS
MULTIGROUP THEORY
NATIONAL ORGANIZATIONS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
ORNL
PERSONAL COMPUTERS
PHYSICS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
SHIELDING
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
TRAINING
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
V CODES