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PSR-0191 EDISTR.

EDISTR, Nuclear Data Base Generator for Internal Radiation Dosimetry Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  EDISTR.
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2. COMPUTERS
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Program name Package id Status Status date
EDISTR PSR-0191/01 Tested 05-JUL-1985

Machines used:

Package ID Orig. computer Test computer
PSR-0191/01 IBM 3033 IBM 3081
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3. DESCRIPTION OF PROGRAM OR FUNCTION

EDISTR uses as input basic radioactive decay data from the Evaluated Nuclear Structure Data File developed by the Nuclear Data Project at Oak Ridge National Laboratory and now maintained by Brookhaven National Laboratory. It  calculates the mean energies and absolute intensities of all principal radiations associated with the radioactive decay of a nuclide. The program provides a physical data base for internal dosimetry calculations or other calculations requiring detailed decay data. The principal calculations performed by EDISTR are the determination of (1) the average energy of beta particles in a beta  transition, (2) the beta spectra as a function of energy, (3) the energies and intensities of X rays and Auger electrons generated by  radioactive decay processes, (4) the bremsstrahlung spectra accompanying beta decay and monoenergetic Auger and internal conversion electrons, and (5) the radiations accompanying spontaneous fission.
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4. METHOD OF SOLUTION

1. Alpha decay. Kinetic energies of the alpha particles and the associated recoil nuclei are computed using conservation of energy and momentum principles. The input data consist of the ground-state  Q value, the various excitation energies of the levels in the daughter nuclide at which the alpha transitions end, and the corresponding alpha intensities.
2. Beta decay. The average energies of the beta particles and the emitted continuous spectra are calculated using the Fermi theory of  beta decay with the input of additional data to determine the forbiddenness of the beta spectra.
3. Electron-Capture decay. The distribution of primary vacancies created in the various atomic shells and subshells as a result of the electron-capture process are calculated using the K/L/M capture  ratios.
4. Internal conversion of gamma rays. This is a process by which the energy of a transition between two states of a nucleus is transferred to an orbital electron. The distribution of the primary  vacancies in the various atomic shells and the energies and intensities of conversion electrons are calculated.
5. X-ray and Auger-electron intensities and energies. Intensities of X rays and Auger electrons are obtained using the numbers of primary vacancies in the various subshells for electron capture or for internal conversion of electrons.
6. Spontaneous fission. The fission decay fraction, the number of neutrons emitted per fission, the mass number of the parent nuclide, and the atomic number of the parent nuclide are used to compute intensities and energies for spontaneous fission fragments, neutrons, beta particles, prompt gamma rays, and delayed gamma rays.  7. Bremsstrahlung radiation. Bremsstrahlung spectra associated with beta particles and monoenergetic conversion and Auger electrons are calculated.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Direct Access Datasets MASTER and SUBMAS may run out of space if more than 10-15 nuclides are done at the same time. Storage space must be increased  in both the JCL and the DEFINE FILE statements in the source program to process more nuclides at one time.
SCHEME has been run with DISSPLA version 8.2. It has not been tested with version 9.
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6. TYPICAL RUNNING TIME

The sample problem, when run on the IBM 3033 computer, required the  following for each of the programs:
         BLDCCT    9 seconds and 800 I/Os
         BUILDU    4 seconds and 4,000 I/Os
         LISDAT   10 seconds and 4,000 I/Os
         EDISTR   21 seconds and 4,000 I/Os
         SCHEME    5 seconds and 3,000 I/Os
PSR-0191/01
NEA-DB executed the test cases included in this package on IBM 3081D.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
PSR-0191/01
BLDCCT              Generation of conversion coefficients
BUILDU              Generation of input data
LISDAT              Listing of data files
SCHEME              Preparation of DISSPLA compressed decay-schemes
                    plot file
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9. STATUS
Package ID Status date Status
PSR-0191/01 05-JUL-1985 Tested at NEADB
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10. REFERENCES:
PSR-0191/01, included references:
- L.T. Dillman:
  EDISTR - A Computer Program to Obtain a Nuclear Decay Data Base
  for Radiation Dosimetry.
  ORNL/TM-6689  (January 1980)
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11. MACHINE REQUIREMENTS:
PSR-0191/01
Main storage requirements for the different modules in  the package a on IBM 3081 are as follows:
                   module      bytes
                   ------      -----
                   EDISTR      440K
                   BLDCCT      116K
                   BUILDU      100K
                   LISDAT      124K
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0191/01 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
PSR-0191/01
The test case was run on IBM 3081D under MVS-SP.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

  Contributed by:
    Oak Ridge National Laboratory
    Oak Ridge, Tennessee
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16. MATERIAL AVAILABLE
PSR-0191/01
File name File description Records
PSR0191_01.003 INFORMATION FILE 180
PSR0191_01.004 EDISTR SOURCE PROGRAM (CARD FORMAT) 5367
PSR0191_01.005 EDISTR SOURCE PROGRAM (FOR IEBUPDTE) 5426
PSR0191_01.006 EDISTR ASSEMBLER ROUTINES (CARD FORMAT) 440
PSR0191_01.007 EDISTR ASSEMBLER ROUTINES (FOR IEBUPDTE) 443
PSR0191_01.008 BLDCCT SOURCE PROGRAM 189
PSR0191_01.009 BUILDU SOURCE PROGRAM 333
PSR0191_01.010 LISDAT SOURCE PROGRAM 353
PSR0191_01.011 JCL FOR TEST CASE EXECUTION 225
PSR0191_01.012 BLDCCT INPUT DATA 15357
PSR0191_01.013 BUILDU INPUT DATA 1604
PSR0191_01.014 EDISTR INPUT DATA FROM UNIT 5 6
PSR0191_01.015 EDISTR INPUT DATA FROM UNIT 47 2
PSR0191_01.016 EDISTR OUTPUT ON UNIT 43 128
PSR0191_01.017 BLDCCT ORIGINAL SOURCE PROGRAM 184
PSR0191_01.018 BLDCCT ORIGINAL JCL 14
PSR0191_01.019 BUILDU ORIGINAL SOURCE PROGRAM 294
PSR0191_01.020 BUILDU ORIGINAL JCL 37
PSR0191_01.021 LISDAT ORIGINAL SOURCE PROGRAM 311
PSR0191_01.022 LISDAT ORIGINAL JCL 24
PSR0191_01.023 EDISTR ORIGINAL SOURCE PROGRAM 5036
PSR0191_01.024 EDISTR ORIGINAL ASSEMBLER ROUTINES 440
PSR0191_01.025 SCHEME ORIGINAL SOURCE PROGRAM 1500
PSR0191_01.026 SCHEME ORIGINAL ASSEMBLER ROUTINES 585
PSR0191_01.027 SCHEME ORIGINAL JCL 47
PSR0191_01.028 BLDCCT ORIGINAL OUTPUT 2
PSR0191_01.029 BUILDU ORIGINAL OUTPUT 24
PSR0191_01.030 LISDAT ORIGINAL OUTPUT 29416
PSR0191_01.031 EDISTR ORIGINAL OUTPUT ON UNIT 6 1
PSR0191_01.032 EDISTR ORIGINAL OUTPUT ON UNIT 43 11
PSR0191_01.033 SCHEME ORIGINAL OUTPUT 128
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: beta spectra, bremsstrahlung, decay spectra, doses, fission spectra, gamma spectra.