1. NAME AND TITLE
BOLD VENTURE IV: A Reactor Analysis Code System.
PRINCIPLE CODE MODULES
VENTURE: Multigroup neutronics finite-difference diffusion theory.
BURNER: Exposure calculation for reactor core analysis.
FUELMANG: Fuel management positioning and accounting.
PERTUBAT: Perturbation reactivity importance analyses.
RODMOD: Control rod positioning.
DEPTHCHARGE: Static and time-dependent perturbation, sensitivity analysis.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
3. CODING LANGUAGE AND COMPUTER
Fortran IV & Assembler, IBM 3033 (C00459/I3033/00).
4. NATURE OF PROBLEM SOLVED
The system of codes can be used to solve nuclear reactor core static neutronics and reactor history
exposure problems. First order perturbation and time-dependent sensitivity theories can be applied.
Control rod positioning may be modeled explicitly and refueling treated with repositioning and recycle.
Special capability is coded to model the continuously fueled core and to solve the importance and
dominant harmonics problems. See the CCC-654/VENTURE-PC package for a subset of this system
for personal computers.
5. METHOD OF SOLUTION
The neutronics problems are solved by applying the multigroup diffusion theory representation of neutron transport applying an overrelaxation inner iteration, outer iteration scheme. Special modeling is used or source correction is done during iteration to solve importance and harmonics problems. No cross section variation or correlation on nuclide concentrations is provided, but a temperature dependence is coded. Steady state condition with continuous fueling is established by a global iterative scheme that applies the criticality search scheme in the neutronics and models fuel movement directly in the exposure code. Time-dependent sensitivity data apply the forward march, reverse importance approach. The codes do not process data from the user input data stream allowing flexible task assignment along selected calculational paths. Multigroup cross section data are produced locally using the PSR-315/AMPX-77 or CCC-450/SCALE-2 code systems to produce resonance shielding (NITAWL) and cell weighted (XSDRN) microscopic cross sections.
Locally, each code is compiled and loaded, and only one version is maintained in a quality
assurance state in load module form. An on-line catalog procedure, installed with system support,
provides job control instructions with nominal default of space allocation to files. Executing the
catalog procedure brings the driver into residence in the memory. The first user input data line must
be the control module name used for the run. Bold Venture reads these data in CCCC ISOTXS
format. AMPX working format libraries can be translated to ISOTXS format using the CONTAC
module of AMPX-77. Alternately PSR-286/COMBINE-PC can be used to process ISOTXS data.
6. RESTRICTIONS OR LIMITATIONS
Limitations are too few to be noteworthy although displaying the restrictions would exceed
7. TYPICAL RUNNING TIME
Running times are problem-dependent.
8. COMPUTER HARDWARE REQUIREMENTS
This system has operated on a number of IBM computers including the 360/75, 360/91, 360/195, 370/155 and 3033 models. Several disks are needed preferably on separate or multiplexed channels. For large problems, disk storage space may become a challenge. Up to 1000 K short words or more of memory may be required with 150 K a practical minimum.
9. COMPUTER SOFTWARE REQUIREMENTS
The ORNL 3033 computers run the OS/VS2 operating system under the JES2 job entry subsystem.
The H-level 21.8 Fortran compiler is in current use. The codes are all written in pre-1978 Fortran
using Hollerith in the guise of REAL numbers and no structured programming or other enhanced
instructions associated with the ANSI-X3.9-1978 standard.
Information on Assembler Routines, Informal Notes, RSIC (July 1984).
D. R. Vondy, "Difficulty Defining the Core Exposure Problem," Memo (December 1985).
D. R. Vondy, T. B. Fowler, G. W. Cunningham, III, "The Bold Venture Computation System for Nuclear Reactor Core Analysis, Version III," ORNL-5711 (June 1981).
D. R. Vondy, T. B. Fowler, G. W. Cunningham, L. M. Petrie, "A Computation System for Nuclear Reactor Core Analysis," ORNL-5158 (April 1977).
D. R. Vondy, T. B. Fowler, G. W. Cunningham, "VENTURE: A Code Block for Solving Multigroup Neutronics Problems Applying the Finite-Difference Diffusion-Theory Approximation to Neutron Transport, Version III," ORNL-5062/R1 (November 1977).
D. R. Vondy, G. W. Cunningham, "Exposure Calculation Code Module for Reactor Core Analysis: BURNER," ORNL-5180 (February 1979).
T. W. Medlin, K. L. Hill, G. L. Johnson, J. E. Jones, D. R. Vondy, "Fuel Management Positioning and Accounting Module: Fuelmang Version V1.11," ORNL-5718 (January 1982).
D. R. Vondy, T. B. Fowler, "The Code PERTUBAT for Processing Neutron Diffusion Theory Neutronics Results for Perturbation Analyses," ORNL-5376 (March 1978).
D. R. Vondy, T. B. Fowler, "RODMOD - A Code for Control Rod Positioning," ORNL-5466 (November 1978).
J. R. White, "The DEPTH-CHARGE Static and Time Dependent Perturbation/Sensitivity System for Nuclear Reactor Core Analysis," ORNL/CSD-78/R1 (May 1984).
D. R. Vondy, T. B. Fowler, "Reference Test Problems for the Venture Neutronics and Related Computer Codes," ORNL/TM-5887 (August 1977).
G. E. Bosler, R. D. O'Dell, W. M. Resnik, "LASIP-III, A Generalized Processor for Standard
Interface Files," LA-6280-MS (April 1976).
11. CONTENTS OF CODE PACKAGE
Version (C00459/I3033/00): referenced documents in 10a. and 3 DS/HD 3.5-in (1.44 MB) diskettes in self-extracting compressed DOS files which contains the Fortran source codes, Assembler Language routines, JCL, sample problem input and output.
12. DATE OF ABSTRACT
June 1984, revised February 1989, September 1990, December 1990, March 1991, February
1995, August 1997.
KEYWORDS: COMPLEX GEOMETRY; DIFFUSION THEORY; MODULAR SYSTEM; MULTIGROUP; NEUTRON; PERTURBATION THEORY; SENSITIVITY ANALYSIS; REACTOR PHYSICS; BURNUP.