NEA-0869 THIDA-2.

1. NAME OR DESIGNATION OF PROGRAM:  THIDA-2.

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.

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.

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.

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-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).

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS

The code APPLE-2 plots the shutdown dose rate and the exact decay heat on a CalComp plotter.

10. 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)

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).

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

MVS/XA (IBM 3083) with compilers VS FORTRAN Level 2.3.0 and assembler ASM H V 02 23.00.

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.

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

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