Computer Programs

NEA-0467 RADHEAT.

NEA-0467 RADHEAT.

RADHEAT, Transport, Heat Generator, Radiation Damage Cross-Sections in Reactor and Shield

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: RADHEAT.

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2. COMPUTERS

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Program name	Package id	Status	Status date
RADHEAT-V3	NEA-0467/01	Tested	01-DEC-1976

Machines used:

Package ID	Orig. computer	Test computer
NEA-0467/01	IBM 370 series	IBM 370 series

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3. NATURE OF PHYSICAL PROBLEM SOLVED

Multi-group cross sections for neutron and photon are generated by using the evaluated nuclear data, ENDF/B, JENDL and DLC-15 for transport, heat generation, and radiation damage calculations in nuclear reactors and shields. The secondary gamma-ray production cross section by the induced reaction and the Bremsstrahlung effect is also generated. The radiation transport problems for shielding designs and safety analyses of fusion and fission reactors are solved.

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4. METHOD OF SOLUTION

A point-wise processing technique and the Bondarenko-type resonance self-shielding factors are adopted to generate multi-group cross sections. One- and two-dimensional Sn transport methods and three-dimensional Monte Carlo method are used for shielding calculation.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The maximum number of neutron and photon fine-groups is 200 and 50, respectively. The maximum number of angular meshes in the macroscopic cross section is 64. The energy ranges from 2.61E-5 eV to 16.74 MeV for neutrons and from 1 KeV to 20 MeV for photons are available.

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6. TYPICAL RUNNING TIME

(a) FAIR-CROSS: At step 1, an iron run with 100 neutron groups takes about 3 minutes. At step 2, a preparation of the macroscopic cross section of water takes about 2 minutes. At step 3, the generation of P5 cross sections takes about 5 secs. for one material.
(b) TWOWAY: A uranium run with 20 photon groups takes about 1 minute.
(c) FDEM: The production of few-group cross sections of one material takes about 10 seconds.
(d) BREM: The production of Bremsstrahlung data of one material takes about 20 seconds.
(e) DIAC: A problem of coupled neutron and photon (100n+20g) groups with 32 angular meshes and 50 spatial intervals takes 30 seconds for one material.
(f) ESPRIT: A problem of coupled neutron and photon (12n+5g) groups with 48 angular meshes and 50x50 spatial intervals takes 2 minutes for one material.
(g) MCACE: The time estimation strongly depends on the particular problem.
(h) VISUAL: The production of a graph takes less than 1 second. (i) POOL: The operation with a command takes about less than 1 second.

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7. UNUSUAL FEATURES OF THE PROGRAM

The angular distribution of the group cross section is expressed by the form of Direct Angular Representation instead of finite Legendre expansion.

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8. RELATED AND AUXILIARY PROGRAMS

RADHAT-V4 can produce also the cross sections compatible with the ANISN, DOT, MORSE codes by using the FAIR-CROSS step 3.

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9. STATUS

Package ID	Status date	Status
NEA-0467/01	01-DEC-1976	Tested at NEADB

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10. REFERENCES

- JSD1000: Multi-Group Cross Section Sets for Shielding Materials
JAERI-M84-038 (1984).

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11. MACHINE REQUIREMENTS

Requires about 1 Mbytes of core storage in addition to the usual complement of tape and the large-size direct access devices.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0467/01	FORTRAN-IV

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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED: FACOM MST.

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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The program is approximately 76000 source cards. Overlay structure is employed.

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15. NAME AND ESTABLISHMENT OF AUTHOR

          N. Yamano et al.
          J.A.E.R.I.
          Tokai Research Establishment
          Tokai-Mura, Ibaraki-Ken, 319-11, Japan

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16. MATERIAL AVAILABLE

NEA-0467/01

File name	File description	Records
NEA0467_01.001	INFORMATION	32
NEA0467_01.002	LIBRARY DATA FOR SAMPLE PROBLEM (ENDF/B-4)	10167
NEA0467_01.003	LIBRARY DATA FOR SAMPLE PROBLEM (JAERI-FAST	5658
NEA0467_01.004	LIBRARY DATA FOR SAMPLE PROBLEM (POPOP-4)	95
NEA0467_01.005	'MACS' SOURCE PROGRAM EBCDIC	20464
NEA0467_01.006	'MACS' OVERLAY CARDS	51
NEA0467_01.007	'MACS' DD CARDS + SAMPLE INPUT DATA (STEP 1)	57
NEA0467_01.008	'TAPEMAKER' SOURCE PROGRAM EBCDIC	786
NEA0467_01.009	'TAPEMAKER' DD CARDS + SAMPLE INPUT DATA	18
NEA0467_01.010	'MACS' DD CARDS + SAMPLE INPUT DATA (STEP 2)	46
NEA0467_01.011	'ANISN-JR' SOURCE PROGRAM EBCDIC	4719
NEA0467_01.012	'ANISN-JR' OVERLAY CARDS	12
NEA0467_01.013	'ANISN-JR' DD CARDS + SAMPLE INPUT DATA	45
NEA0467_01.014	'CONVERT' SOURCE PROGRAM EBCDIC	23
NEA0467_01.015	'CONVERT' DD CARDS	5
NEA0467_01.016	'MACS' (STEP 1) SAMPLE PRINTED OUTPUT	1730
NEA0467_01.017	'TAPEMAKER' SAMPLE PRINTED OUTPUT	29
NEA0467_01.018	'MACS' (STEP 2) SAMPLE PRINTED OUTPUT	1760
NEA0467_01.019	'ANISN-JR' SAMPLE PRINTED OUTPUT	1885

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17. CATEGORIES

J. Gamma Heating and Shield Design

Keywords: cross sections, discrete ordinate method, few-group, gamma radiation, heat transfer, multigroup, one-dimensional, radiation heat, self-shielding, transport theory.