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NEA-0869 THIDA-2.

THIDA, Transmutation, Hazard Potential, Dose Rate in Fusion Reactor
THIDA-2, Transmutation, Activation, Decay Heat, Dose Rate in Fusion Reactor

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1. NAME OR DESIGNATION OF PROGRAM:  THIDA-2.
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2. COMPUTERS
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Program name Package id Status Status date
THIDA-2 NEA-0869/02 Tested 18-JUN-1990

Machines used:

Package ID Orig. computer Test computer
NEA-0869/02 FACOM M-380 IBM 3083
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3. DESCRIPTION OF PROBLEM OR FUNCTION

THIDA-2 calculates radio- activity, decay heat, and dose rate for a fusion reactor using one-, two-, or three-dimensional models.
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4. METHOD OF SOLUTION

Firstly, the neutron flux in and around a fusion device during operation is calculated. Depending on whether one-, two-, or three-dimensional geometry is required, one of the transport codes ANISN, DOT-3.5, or MORSE-CG, is used, respectively.  The neutron flux is used as input for the code ACT4. ACT4 calculates the induced activity, the approximate decay heat, and the delayed gamma-ray source after a pulsed operation of the fusion device. The  Matrix Exponential Method is used to solve the decay chain equations to obtain time dependent nuclide densities. The delayed gamma-ray source serves as input for the transport calculation of the delayed  gamma-ray flux during shutdown. The same transport code is used for  the calculation of the neutron and the delayed gamma-ray fluxes. Finally, the gamma-ray flux is converted to shutdown dose rate, and  the exact decay heat is calculated.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

(i) Sequential decay of two short-lived nuclides cannot be calculated accurately.
(ii) Reactions of neutrons with nuclear reaction products are not considered.
(iii) Changes in neutron flux caused by transmutation cannot be treated in a single calculation.
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6. TYPICAL RUNNING TIME

With 116 spatial mesh point: 5 min. for activated nuclide distribution; 6.5 min. for gamma-ray dose distribution.
NEA 0869/01: NEA-DB executed the test cases on IBM 3084Q. The following CPU times were required: ACT3: 4 min 37 sec; GSOURCE: 0.86 sec; ANISN: 3 min 09 sec.
NEA-0869/02
NEA-DB ran the test case included in this package on an IBM 3083 computer. The following execution times were required for the different steps: Generate GICX40 library: 15.2 secs; generate GROUPIN library: 12.6 secs; 1-dimensional calculation: 10.4 secs (ANISN, step 1), 8.5 secs (ACT4, step 2), 8.0 secs (ANISN step 3), 0.4 secs (APPLE, step 4); 2-dimensional calculation: 0.5 secs (x-sec edit, step 1), 195.3 secs (DOT3.5 step 2), 27.5 secs (ACT4, step 3), 0.7 secs (x-sec edit, step 4), 182.0 secs (DOT3.5, step 5), 0.7 secs (APPLE, step 6); 3-dimensional calculation: 388.9 secs (MORSE-I, step 1), 3.0 secs (ACT4, step 2), 240.0 secs (MORSE-I, step 3), 56.0 secs (TOPIC, step 4).
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The code APPLE-2 plots the shutdown dose rate and the exact decay heat on a CalComp plotter.
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9. STATUS
Package ID Status date Status
NEA-0869/02 18-JUN-1990 Tested at NEADB
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10. REFERENCES:
NEA-0869/02, included references:
- Y. Seki, H. Hiida, H. Kawasaki and K. Yamada:
  THIDA-2: An Advanced Code System for Calculation of Transmutation,
  Activation, Decay Heat and Dose Rate
  JAERI 1301  (March 1986)
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11. MACHINE REQUIREMENTS

Data transmissions between codes are done using scratch devices. In the radioactivity calculation by ACT4, in  addition to standard input and ouput devices, 4 scratch devices are  used for data libraries and neutron flux input; one scratch device is used to write gamma-ray source; and 4 storage devices are required for data manipulation.
NEA 0869/01: Main storage requirements on IBM 3084Q are 159K bytes (GSOURCE); 1475K bytes (ANISN).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0869/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-0869/02
MVS/XA (IBM 3083) with compilers VS FORTRAN Level 2.3.0 and assembler ASM H V 02 23.00.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The following data libraries (included in the THIDA-2 system) are required by THIDA-2 to calculate the shutdown dose rate:
(1) for the neutron transport calculation, a 42-group neutron cross  section library, which is part of the coupled 42-group neutron and 21-group gamma-ray cross section library GICX40;
(2) a transmutation and decay chain data library, CHAINLIB;
(3) a 42-group transmutation cross section data library, CROSSLIB, which has the same energy group structure as GICX40;
(4) a 54-group gamma-ray cross section library, GROUPIN, for delayed gamma-ray transport calculations for energies from 0.03 MeV to 3.0 MeV. A 78-group gamma-ray cross section library for energies up to 7.6 MeV may optionally be used;
(6) gamma-ray flux to dose rate conversion data, GFLXDOSE.
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:
      Fusion Reactor System Laboratory
      Department of Large Tokamak Development
      Naka Fusion Research Establishment
      Japan Atomic Energy Research Institute
      Naka-machi, Naka-Gun, Ibaraki-ken, JAPAN
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16. MATERIAL AVAILABLE
NEA-0869/02
File name File description Records
NEA0869_02.001 Information file 615
NEA0869_02.002 Converter to make GICX40 library 15
NEA0869_02.003 JCL to make GICX40 12
NEA0869_02.004 BCD data of GICX40 181440
NEA0869_02.005 Converter to make GROUP library 15
NEA0869_02.006 JCL to make GROUP library 12
NEA0869_02.007 BCD data to make GROUP library 129600
NEA0869_02.008 1-dim, Step-1 ANISN source 4145
NEA0869_02.009 1-dim, Step-1 Sample input 35
NEA0869_02.010 1-dim, Step-1 JCL 34
NEA0869_02.011 1-dim, Step-1 Sample output 1057
NEA0869_02.012 1-dim, Step-2 ACT4 source 5148
NEA0869_02.013 1-dim, Step-2 Sample input 19
NEA0869_02.014 1-dim, Step-2 BCD library data (CHAIN-LIB) 2380
NEA0869_02.015 1-dim, Step-2 BCD library data (CROSS-LIB) 2437
NEA0869_02.016 1-dim, Step-2 BCD library data (GAMMA-LIB) 1511
NEA0869_02.017 1-dim, Step-2 JCL 25
NEA0869_02.018 1-dim, Step-2 Sample output 1060
NEA0869_02.019 1dim, Step-3 ANISN source 4149
NEA0869_02.020 1dim, Step-3 Sample input 35
NEA0869_02.021 1-dim, Step-3 JCL 33
NEA0869_02.022 1-dim, Step-3 Sample output 1235
NEA0869_02.023 1-dim, Step-4 APPLE source 5651
NEA0869_02.024 1-dim, Step-4 Sample input 29
NEA0869_02.025 1-dim, Step-4 BCD library data (GFLXDOSE) 13
NEA0869_02.026 1-dim, Step-4 JCL 26
NEA0869_02.027 1-dim, Step-4 Sample output 411
NEA0869_02.028 2-dim, Step-1 MIXTURE-EDIT source 50
NEA0869_02.029 2-dim, Step-1 Sample input 1
NEA0869_02.030 2-dim, Step-1 JCL 16
NEA0869_02.031 2-dim, Step-1 Sample output 252
NEA0869_02.032 2-dim, Step-2 DOT3.5 source 7521
NEA0869_02.033 2-dim, Step-2 Sample input 75
NEA0869_02.034 2-dim, Step-2 JCL 39
NEA0869_02.035 2-dim, Step-2 Sample output 2823
NEA0869_02.036 2-dim, Step-3 Sample input 19
NEA0869_02.037 2-dim, Step-3 JCL 25
NEA0869_02.038 2-dim, Step-3 Sample output 884
NEA0869_02.039 2-dim, Step-4 MIXTURE-EDIT source 50
NEA0869_02.040 2-dim, Step-4 Sample input 1
NEA0869_02.041 2-dim, Step-4 JCL 13
NEA0869_02.042 2-dim, Step-4 Sample output 253
NEA0869_02.043 2-dim, Step-5 DOT3.5 source 7394
NEA0869_02.044 2-dim, Step-5 Sample input 52
NEA0869_02.045 2-dim, Step-5 JCL 38
NEA0869_02.046 2-dim, Step-5 Sample output 3391
NEA0869_02.047 2-dim, Step-6 Sample input 34
NEA0869_02.048 2-dim, Step-6 JCL 26
NEA0869_02.049 2-dim, Step-6 Sample output 455
NEA0869_02.050 3-dim, Step-1 MORSE-I source 9978
NEA0869_02.051 3-dim, Step-1 Sample input 97
NEA0869_02.052 3-dim, Step-1 JCL 21
NEA0869_02.053 3-dim, Step-1 Sample output 1485
NEA0869_02.054 3-dim, Step-2 Sample input 20
NEA0869_02.055 3-dim, Step-2 JCL 25
NEA0869_02.056 3-dim, Step-2 Sample output 865
NEA0869_02.057 3-dim, Step-3 MORSE-I source 10123
NEA0869_02.058 3-dim, Step-3 Sample data 89
NEA0869_02.059 3-dim, Step-3 JCL 21
NEA0869_02.060 3-dim, Step-3 Sample output by the Data Bank 1455
NEA0869_02.061 3-dim, Step-3 Sample output by the author 2049
NEA0869_02.062 3-dim, Step-4 TOPIC source 2595
NEA0869_02.063 3-dim, Step-4 Sample input 97
NEA0869_02.064 3-dim, Step-4 JCL 9
NEA0869_02.065 3-dim, Step-4 Sample output 402
NEA0869_02.066 Dummy plotter routines and CLOCKM 27
NEA0869_02.067 Assembler routine ICOMPL 36
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17. CATEGORIES
  • X. Magnetic Fusion Research

Keywords: activation, dose rates, fusion reactors, gamma radiation, neutron reactions, transmutation.