Multidimensional multigroup diffusion-depletion calculations on the microcomputer
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5199890
As part of the Idaho National Engineering Laboratory personal computer (PC)-based reactor physics code system, a portion of the BOLD VENTURE modular code system developed over a period of years at Oak Ridge National Laboratory was recompiled and made operable on IBM or compatible microcomputers. The PC version, labeled VENTURE-PC, utilizes the VENTURE multidimensional, multigroup diffusion module, and exposure module based on the BURNER code, and various control and input modules. The code system is variably dimensioned and has many input options, making it very flexible and powerful for the calculation of diffusion-depletion problems. In addition to being applicable to general reactor physics studies, the code system should prove useful for nuclear engineering student design projects and general graduate student use.
- OSTI ID:
- 5199890
- Report Number(s):
- CONF-890604--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
- Country of Publication:
- United States
- Language:
- English
Similar Records
New versions of VENTURE/PC, a multigroup, multidimensional diffusion-depletion code system
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
Conference
·
Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7089785
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
Technical Report
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:5216999
VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system
Technical Report
·
Sat Nov 30 23:00:00 EST 1991
·
OSTI ID:5513456
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
B CODES
BURNUP
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
DESIGN
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
ENGINEERING
EQUATIONS
GROUP THEORY
IBM COMPUTERS
IDAHO NATIONAL ENGINEERING LABORATORY
MATHEMATICS
MEMORY DEVICES
MICROCOMPUTERS
NATIONAL ORGANIZATIONS
NEUTRON DIFFUSION EQUATION
NUCLEAR ENGINEERING
ONE-DIMENSIONAL CALCULATIONS
ORNL
PERSONAL COMPUTERS
PHYSICS
PROGRAMMING
REACTOR PHYSICS
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
USES
V CODES
220100* -- Nuclear Reactor Technology-- Theory & Calculation
B CODES
BURNUP
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
DESIGN
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
ENGINEERING
EQUATIONS
GROUP THEORY
IBM COMPUTERS
IDAHO NATIONAL ENGINEERING LABORATORY
MATHEMATICS
MEMORY DEVICES
MICROCOMPUTERS
NATIONAL ORGANIZATIONS
NEUTRON DIFFUSION EQUATION
NUCLEAR ENGINEERING
ONE-DIMENSIONAL CALCULATIONS
ORNL
PERSONAL COMPUTERS
PHYSICS
PROGRAMMING
REACTOR PHYSICS
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
USES
V CODES