CCC-0459: BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup

Program-name Package-ID Status BOLD/VENTURE-4 CCC-0459/01 Tested VENTURE PC CCC-0459/02 Obsolete VENTURE PC CCC-0459/03 Obsolete VENTURE PC CCC-0459/04 Obsolete

Machines used: Package-ID Orig.Computer Test Computer CCC-0459/01 IBM 3033 IBM 3081

3. DESCRIPTION OF PROGRAM OR FUNCTION - The system of codes can be used to solve nuclear reactor core static neutronics and reactor history exposure problems.
BOLD/VENTURE-4: 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.
The modules of the code system are:
     VENTNEUT:    VENTURE neutronics module;
     DRIVER &     Control module;
     CONTRL:
     BURNER:      Exposure calculation for reactor core analysis;
     FILEDTOR:    File editor
     INPROSER:    Input processor;
     EXPOSURE:    BURNER code module;
     REACRATE:    Reaction rate calculation;
     CNTRODPO:    Control rod positioning;
     FUELMANG:    Fuel management positioning and accounting;
     PERTUBAT:    Perturbation reactivity importance analyses;
                  sensitivity analysis;
     DEPTHMOD:    Static and time-dependent perturbation
                  sensitivity analysis;
The special processors are:
     DVENTR:      Handles the input to the VENTURE module;
     DCMACR:      Converts CITATION macroscopic cross sections to
                  microscopic cross sections;
     DCRSPR       Produces input for the CROSPROS module;
     DUTLIN:      Adds or replaces problem input data without
                  exiting the program;
     DENMAN:      Repositions fuel;
     DMISLY:      Miscellaneous tasks.
Standard interface files between modules are binary sequential files that follow a standardized format.
VENTURE-PC: The microcomputer version is a subset of the mainframe version. The modules and special processors which are not part of VENTURE-PC are: REACRATE, CNTRODPO, PERTUBAT, FUELMANG, DEPTHMOD, DMISLY.

4. METHOD OF SOLUTION -
BOLD-VENTURE-4: 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 applies 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-0063/AMPX II or CCC-0450/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 makes the driver memory resident. The first user input data line must be the control module name used for the run.
VENTURE-PC: The VENTURE module applies the finite-difference diffusion or a simple P1 approximation. VENTURE uses an outer-inner iteration scheme with several different data handling methods. Overrelaxation is applied to the inner and outer iterations, and succeeding flux iterates may be accelerated with the Chebychev process. - The BURNER code (module EXPOSURE) uses a difference formulation based on average generation rates; or a matrix exponential formulation to approximate the solution of the coupled burnup differential equations; or an explicit solution for simply coupled nuclide chains. Space dependence is included by working with zone averaged fluxes.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME - Running times are problem-dependent. On an IBM PC/XT with a math co-processor, the problem BWR12AC.INP took about 10 minutes; the input TWODXY.INP took about 60 minutes (the operating system was DOS 3.3).

CCC-0459/01:

NEA-DB executed the test cases included in the package on IBM 3081K. CPU times required were 566 seconds for the super sample problem; 24 seconds for sample problem 1; and 6 seconds for sample problem 2.

7. UNUSUAL FEATURES OF THE PROGRAM -

9. STATUS
CCC-0459/01: 05-JUN-1985 Tested at NEADB
CCC-0459/02: 17-OCT-1994 Obsolete
CCC-0459/03: 25-AUG-1995 Obsolete
CCC-0459/04: 17-JUL-1998 Obsolete

10. REFERENCES  -
CCC-0459/01:
- D.R. Vondy:
  Difficulty Defining the Core Exposure Problem.
  RSIC Note  (December 30, 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) + Appendix B+C
- D.R. Vondy, T.B. Fowler, G.W. Cunningham:
  A Computation System for Nuclear Reactor Core Analysis
  ORNL-5158  (April 1977)
- D.R. Vondy, T.B. Fowler, G.W. Cunningham, L.M. Petrie:
  VENTURE: A Code Block for Solving Multigroup Neutronics Problems
  Applying the Finite-Difference Diffusion-Theory Approximation to
  Neutron Transport, Version II
  ORNL-5062/R1  (November 1977)
- D.R. Vondy, G.W. Cunningham:
  Exposure Calculation Code Module for Reactor Core Analyses: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)
- J.R. White, "The DEPTH-CHARGE Static and Time-Dependent
  Perturbation/Sensitivity System for Nuclear Reactor Core
  Analysis," ORNL/CSD-78/R1 (April 1985)
- D.R. Vondy, T.B. Fowler:
  RODMOD - A Code for Control Rod Positioning.
  ORNL-5466  (November 1978)
- 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. MACHINE 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 multi- plexed channels. For large problems, disk storage space may become a challenge. Up to 1000K short words or more of memory may be required with 150K a practical minimum.
VENTURE-PC. The program requires about 5MB of hard disk storage to hold the executable files and files generated by the code. The program also requires a math co-processor. The 16-bit version of VENTURE-PC requires 640K of conventional RAM. The 32-bit version requires 4MB of memory.

CCC-0459/01:

Main storage requirements to execute the test cases of the package on IBM 3081K are 1252K bytes for the super sample problem; 588K bytes for sample problem 1; and 460K bytes for sample problem 2.

12. PROGRAMMING LANGUAGE(S) USED -
CCC-0459/01: FORTRAN+ASSEMBLER

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - The ORNL computers run the OS/VS2 operating system under the JES2 job entry subsystem. The H-level 21.8 FORTRAN compiler using Hollerith in the guise of REAL numbers and no structured programming or other enhanced instructions associated with the ANSI-X3.9-1978 standard.

CCC-0459/01:

The test cases were executed under MVS-SP using the FORTRAN H EXTENDED (IFEAAB) compiler and ASSEMBLER H (IEV90).

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHORS -
Developed by:   Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Contributed by: Radiation Shielding Information Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

17. CATEGORIES -

- C. Static Design Studies
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
- F. Space
Time Kinetics, Coupled Neutronics Hydrodynamics Thermodynamics
- K. Reactor Systems Analysis

Keywords: BURNUP, CONTROL ELEMENTS, FUEL MANAGEMENT, NEUTRON TRANSPORT THEORY, PERTURBATION, REACTOR CORES, SENSITIVITY, SENSITIVITY ANALYSIS