last modified: 04-AUG-1988 | catalog | categories | new | search |

NESC9888 NUTRAN.

NUTRAN, Doses by Radionuclide Migration from Nuclear Waste Storage

top ]
1. NAME OR DESIGNATION OF PROGRAM:  NUTRAN.
top ]
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
NUTRAN NESC9888/01 Tested 04-AUG-1988

Machines used:

Package ID Orig. computer Test computer
NESC9888/01 IBM 370 series IBM 3090
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

NUTRAN is a system of four computer programs for calculating the dose to humans from radionuclides carried out of deep geologic nuclear waste repositories by ground water. NUTRAN is composed of the FORTRAN programs - ORIGEN1 and BIODOSE and the PL/I programs - WASTE and PLOT. ORIGEN1, developed by Oak Ridge National Laboratory, generates an inventory of radionuclides as a function of time; BIODOSE computes the doses to humans which result from any releases of radioactivity into the biosphere. WASTE models the release of radionuclides from a repository and their transport in the subsurface, and PLOT combines the results of BIODOSE and WASTE - dose per MWe-yr released and releases in units of MWe-yr of waste -  to obtain doses and generate dose plots. The ORIGEN1 program developed by ORNL is not included.
top ]
4. METHOD OF SOLUTION

The NUTRAN model incorporates the following features: refilling of the repository cavity with water; leaching of the waste matrix; dissolution of the radioactive elements in the waste; transport of waste by ground water through the repository, surrounding strata, and adjacent aquifers; withdrawal of contaminated ground water through wells; transport of waste in surface waters and associated ecosystems; and human exposure and dose mechanisms. A three-dimensional ground water flow field is modeled as a network of one-dimensional flow paths or "stream tubes". The stream tube approach allows a relatively straightforward representation of small discontinuities (e.g. faults, boreholes), avoiding the difficulties which are encountered in solving time-dependent solute migration problems by finite-element or finite-difference methods. For each stream tube, nuclide transport is solved explicitly by a Green's function (impulse response) approach. The biosphere transport is modeled by a system of sediment, water, and soil compartments. Radionuclide concentrations  in these compartments are used to compute doses to humans.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME:
NESC9888/01
NEA-DB ran the test cases included in this package on an IBM 3090 computer. The total execution time of all modules for all three cases was less than 20 CPU seconds.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS:
top ]
9. STATUS
Package ID Status date Status
NESC9888/01 04-AUG-1988 Tested at NEADB
top ]
10. REFERENCES

- M.J. Bell
  ORIGEN: The ORNL Isotope Generation and Depletion Code,
  ORNL-4628, May 1973.
- L.E. Berman, D.A. Ensminger, M.S. Giuffre, C.M. Koplik, S.G.
  Oston, G.D. Pollak and B.I. Ross
  Analyses of Some Nuclear Waste Management Options,
  UCRL-13917, Vols. I and II, October 1978.
NESC9888/01, included references:
- C.M. Koplik, J.Y. Nalbandian and J.I. Scott:
  User's Guide to NUTRAN: A Computer Program for Long-Term
  Repository Safety Analysis.
  TR-3854-5  (June 1983)
top ]
11. MACHINE REQUIREMENTS:  1Mbyte (BIODOSE), 512K bytes (WASTE), 512K bytes (PLOT).
NESC9888/01
All test cases could be run on an IBM 3090 in 1208K bytes of main storage.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC9888/01 FORTRAN+PL/I
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/VS1.
NESC9888/01
MVS/XA (IBM 3090).
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Well
concentration calculations require the use of the proprietary IMSL mathematical subroutine library, and plot output is produced using the proprietary ISSCO graphics software, DISSPLA. Neither of these software packages is supplied.
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

          C.M. Koplik, J.Y. Nalbandian, and J.I. Scott
          The Analytic Sciences Corporation
top ]
16. MATERIAL AVAILABLE
NESC9888/01
File name File description Records
NESC9888_01.001 INFORMATION FILE 322
NESC9888_01.002 BIODOSE SOURCE (FORTRAN) 5228
NESC9888_01.003 WASTE SOURCE (PLI/I) 6302
NESC9888_01.004 PLOT SOURCE (PL/I) 1906
NESC9888_01.005 EIGRF REPLACEMENT SOURCE (FORTRAN) 2580
NESC9888_01.006 LINV2F REPLACEMENT SOURCE (FORTRAN) 592
NESC9888_01.007 MMBSK0 REPLACEMENT SOURCE (FORTRAN) 117
NESC9888_01.008 NUCLIDE CONTROL FILE 33
NESC9888_01.009 PARAMETER FILE 2
NESC9888_01.010 INVENTORY FILE 2
NESC9888_01.011 JCL + I/P DATA 975
NESC9888_01.012 ORIGINAL JCL 638
NESC9888_01.013 TEST CASE 1 O/P 2781
NESC9888_01.014 TEST CASE 2 O/P 6815
NESC9888_01.015 TEST CASE 3 O/P 2299
top ]
17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • R. Environmental and Earth Sciences

Keywords: doses, ground water, radiation doses, radioactive waste storage, radionuclide migration.