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CCC-0459 BOLD-VENTURE.

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

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1. NAME OR DESIGNATION OF PROGRAM:  BOLD-VENTURE.
A Reactor Analysis System, Version IV.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
BOLD/VENTURE-4 CCC-0459/01 Tested 05-JUN-1985

Machines used:

Package ID Orig. computer Test computer
CCC-0459/01 IBM 3033 IBM 3081
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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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.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The code VENTURE-PC comes with VIP  (VENTURE Interactive Procesor). VIP interactively generates an input file for VENTURE-PC.
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9. STATUS
Package ID Status date Status
CCC-0459/01 05-JUN-1985 Tested at NEADB
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10. REFERENCES:
CCC-0459/01, included references:
- 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)
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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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0459/01 FORTRAN+ASSEMBLER
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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).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
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16. MATERIAL AVAILABLE
CCC-0459/01
File name File description Records
CCC0459_01.003 INFORMATION FILE 106
CCC0459_01.004 ALIAS SRCE TO CREATE SUBROUTINE LIB (PL/I) 63
CCC0459_01.005 SUBROUTINE LIBRARY ROUTINES (ASSEMBLER) 2590
CCC0459_01.006 JCL TO CREATE SUBROUTINE LIBRARY 62
CCC0459_01.007 SCALE DRIVER (ASSEMBLER) 276
CCC0459_01.008 LPGETMDL DRIVER (ASSEMBLER) 350
CCC0459_01.009 LPREADER DRIVER (ASSEMBLER) 121
CCC0459_01.010 LPGETPRM DRIVER (ASSEMBLER) 55
CCC0459_01.011 CONTROL1 CONTROL MODULE 2695
CCC0459_01.012 INPROSER INPUT PROCESSOR 5276
CCC0459_01.013 INDVENTR-DVENTR SPECIAL INPUT PROCESSOR 4394
CCC0459_01.014 INDCRSPR-DCRSPR SPECIAL INPUT PROCESSOR 1466
CCC0459_01.015 INDUTLIN-DUTLIN SPECIAL INPUT PROCESSOR 1102
CCC0459_01.016 INDCMACR-DCMACR SPECIAL INPUT PROCESSOR 198
CCC0459_01.017 FILEDTOR FILE EDITOR 6342
CCC0459_01.018 CROSPROS X-SEC PROCESSOR 7326
CCC0459_01.019 VENTNEUT VENTURE NEUTRONICS CALCULATION 45806
CCC0459_01.020 REACRATE REACTION RATE CALCULATION 6515
CCC0459_01.021 CNTRODPO-RODMOD CONTROL ROD POSITIONING 4974
CCC0459_01.022 EXPOSURE-BURNER EXPOSURE CALCULATION 24302
CCC0459_01.023 PERTUBAT PERTURBATION CALCULATION 18476
CCC0459_01.024 DMISLY SPECIAL PROCESSOR 4342
CCC0459_01.025 DENMAN SPECIAL PROCESSOR 2333
CCC0459_01.026 FUELMNGR FUEL MANAGEMENT ) 18186
CCC0459_01.027 DEPTHMOD-DEPTH SOURCE PROGRAM 7329
CCC0459_01.028 CHARGEMD-CHARGE SOURCE PROGRAM 11642
CCC0459_01.029 SUBMRGMD-SUBMRG SOURCE PROGRAM 1944
CCC0459_01.030 SENSENMD-SENSEN SOURCE PROGRAM 1151
CCC0459_01.031 JCL TO COMPILE AND LINK SOURCE PROGRAMS 632
CCC0459_01.032 STAND-ALONE VENTURE STORAGE CALCULATION 1806
CCC0459_01.033 STAND-ALONE BURNER STORAGE CALCULATION 949
CCC0459_01.034 JCL TO RUN SUPER SAMPLE PROBLEM 84
CCC0459_01.035 SUPER SAMPLE PROBLEM INPUT DATA 621
CCC0459_01.036 SUPER SAMPLE PROBLEM PRINTED OUTPUT 6772
CCC0459_01.037 JCL TO RUN SAMPLE PROBLEM 1 136
CCC0459_01.038 SAMPLE PROBLEM 1 INPUT DATA 1199
CCC0459_01.039 SAMPLE PROBLEM 1 PRINTED OUTPUT 4767
CCC0459_01.040 JCL TO RUN SAMPLE PROBLEM 2 115
CCC0459_01.041 SAMPLE PROBLEM 2 INPUT DATA 92
CCC0459_01.042 SAMPLE PROBLEM 2 PRINTED OUTPUT 1057
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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.