last modified: 11-JUN-1982 | catalog | categories | new | search |

NEA-0622 ORIGEN-JR.

ORIGEN-JR, Radiation Source and Nuclide Transmutation with In-Core Burnup

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1. NAME OR DESIGNATION OF PROGRAM:  ORIGEN-JR.
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2. COMPUTERS
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Program name Package id Status Status date
ORIGEN-JR NEA-0622/01 Tested 11-JUN-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0622/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

ORIGEN-JR, which has been developed from ORIGEN, calculates radiation sources and analyses nuclide transmutations. The calculation of neutron source spectra has been revised extensively. In addition to the spectrum indices adopted in ORIGEN, one-group cross sections for each reaction can be used to treat precisely the burnup conditions in a reactor core. Neutron and gamma-ray source data are generated in the same format as in the shielding codes QAD-PS, ANISN and DOT.
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4. METHOD OF SOLUTION

The code solves the equations of radioactive nuclide transmutation and calculates radiation sources. Energy spectra of neutron sources in spontaneous fission and (alpha, n) reactions of eight nuclides (9Be, 10B, 11B, 13C, 14N, 170, 180 and 19F) are available. Complex decay and transmutation schemes and one-group reaction cross sections can be treated.

A Matrix Exponential method is used to solve the resultant large system of coupled, linear, first-order, ordinary differential equations with constant coefficients.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The code will handle 850 nuclides of which no more than 500 are described as light elements, no more than 120 are actinides and their decay daughters,  and no more than 500 are fission products.

Fission products are produced by fission rates of five different actinides. In addition, there may be no more than 3000 non-zero elements in the nuclear transmutation matrix. Numerical inaccuracies due to too coarse a time spacing are indicated by a warning message.
Neutron spectra due to (alpha, n) reaction can be calculated by no more than 61 actinides and 8 light nuclides.
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6. TYPICAL RUNNING TIME

Running time mainly depends on the (alpha,n)  reaction calculation. A typical problem with 7 actinides and 2 light nuclides takes about 3 minutes on a FACOM 230/75 (equivalent to IBM  370/165).
NEA-DB executed the test case on IBM 3033 in 140 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

ORIGEN, QAD-P5, ANISN, DOT, MORSE,  etc. ELIESE-3, RADHEAT-V3.
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9. STATUS
Package ID Status date Status
NEA-0622/01 11-JUN-1982 Tested at NEADB
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10. REFERENCES

- M.J. Bell:
  ORIGEN - The ORNL Isotope Generation and Depletion Code
  ORNL-4628 (1973).
- D.L. Lessor, R.E. Schenter:
  Neutron Spectra from (Alpha, n) Reactions in Plutonium Compounds
  Calculated from Hauser-Feshbach Reaction Theory
  BNWL-B-109 (1971).
- S. Igarasi:
  Program ELIESE-3 - Program for Calculation of the Nuclear Cross
  Sections by Using Local and Non-Local Optical Models and
  Statistical Models
  JAERI-1224 (1972).
- K. Koyama, et al.:
  RADHEAT-V3 - A Code System for Generating Coupled Neutron and
  Gamma-Ray Group Constants and Analyzing Radiation Transport
  JAERI-M 7155 (1977).
NEA-0622/01, included references:
- K. Koyama, N. Yamano, S. Miyasaka:
  A computer code for calculating radiation sources and analizing
  nuclide transmutations, JAERI-M 8229 (May 1979)
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11. MACHINE REQUIREMENTS

Requires 680 K byte of core storage in addition to the usual complement of direct access devices and auxiliary equipment of punch and printer. There is no need for clock sampling.
The test case runs on IBM 3033 in 650 Kbytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0622/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
OS370/033 VS2 03.8G (IBM 3033).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Kinji Koyama, Naoki Yamano, Shun-ich Miyasaka
          Japan Atomic Energy Research Institute
          Tokai-mura, Ibaraki-ken
          Japan.
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16. MATERIAL AVAILABLE
NEA-0622/01
File name File description Records
NEA0622_01.003 ORIGEN-JR INFORMATION FILE 152
NEA0622_01.004 ORIGEN-JR, SOURCE CARD IMAGES (FORTRAN-4) 3856
NEA0622_01.006 ORIGEN-JR, INPUT DATA FOR SAMPLE CASE 39
NEA0622_01.007 NUCLIDE LIB DATA (LIGHT ELEMENTS) 1265
NEA0622_01.008 NUCLIDE LIB DATA (HEAVY ELEMENTS) 505
NEA0622_01.009 FISSION PRODUCTS (NUCLIDES) 2305
NEA0622_01.010 PHOTON LIB DATA (LIGHT ELEMENTS) 253
NEA0622_01.011 PHOTON LIB DATA (HEAVY ELEMENTS) 202
NEA0622_01.012 FISSION PRODUCTS (PHOTONS) 461
NEA0622_01.013 (ALPHA,N) LIB DATA 7409
NEA0622_01.014 (ALPHA,N) LIB DATA PREPARATION PROGRAM 23
NEA0622_01.015 STOPPING POWER LIB DATA 232
NEA0622_01.016 STOPPING POWER LIB DATA PREPARATION PROGRAM 14
NEA0622_01.017 ORIGEN-JR, OUTPUT OF SAMPLE CASE 4093
NEA0622_01.018 ORIGEN-JR, JCL TO RUN SAMPLE CASE 129
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, cross sections, decay, fission products, gamma radiation, neutron spectra, optical models, radioactivity.