Computer Programs
NEA-1581 ART MOD2.
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NEA-1581 ART MOD2.

ART MOD2, Fission Product Migration in Primary System and Containment

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1. NAME OR DESIGNATION OF PROGRAM

ART MOD2.

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2. COMPUTERS

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Program name Package id Status Status date
ART MOD2 NEA-1581/02 Arrived 12-FEB-2015

Machines used:

Package ID Orig. computer Test computer
NEA-1581/02 FACOM M-780,SUN
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3. DESCRIPTION OF PROGRAM OR FUNCTION

ART MOD2 aims at a comprehensive analysis for the FP behaviour in primary system and in containment during severe accidents and therefore the code considers the removal of radionuclides of up to 60 materials including chemical compounds by natural deposition and by the engineered safety features (ESF) such as spray systems. As for the natural deposition of radionuclides, the code can consider the phenomena such as gravitational settling, thermophoresis, diffusiophoresis, Brownian diffusion, diffusion under laminar or turbulent flows, resuspension, condensation, chemisorption and revaporization. The code also models the aerosol growth by agglomeration of aerosols and condensation/ evaporation of volatile material at the aerosol surface. Recently, the models for iodine chemistry in containment sump water was incorporated.

 

ART MOD2 was modified in January 2015 to correct coding errors and improve the vibration of the calculation result of water (H2O) vapor.

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4. METHODS

Equations relating to mass and energy conservation.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The code does not consider the chemical reactions among FP elements. The present version also does not model aerosol growth by hygroscopicity.

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6. TYPICAL RUNNING TIME

A few hours for analysis of JAERI's WIND or WAVE experiment by SUN Sparc 20 Workstation.

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7. UNUSUAL FEATURES OF THE PROGRAM

ART Mod2 has a fast running capability to cover various accident sequences in a Probabilistic Safety Assessment (PSA). Since the code is a module of JAERI's integrated severe accident analysis code, THALES-2, the improvement of ART can be directly reflected on the source term analysis with THALES-2.

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8. RELATED OR AUXILIARY PROGRAMS

THALES-2 developed by JAERI; A Computer Code for Coupled Thermal-Hydraulics and FP Transport Analyses for Severe Accident at LWRs.

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9. STATUS
Package ID Status date Status
NEA-1581/02 12-FEB-2015 Masterfiled Arrived
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10. REFERENCES
  • Ishigami, T. et. al.:
    User's Manual of ART Code for Analyzing FP Transport Behaviour During Core Meltdown Accident.
    JAERI-M 88-093 (1988) (in Japanese)

  • Kajimoto, M., et. al.:
    The Validation of the ART Code Through Comparison with NSPP Experiments in the Steam-Air Atmosphere.
    NEA/CEC/CEA CSNI Workshop on Aerosol Behaviour and Thermal Hydraulics in Containment, Fontenay-aux-Roses, 145 (1990)

  • Kajimoto, M., et. al.:
    Development of THALES-2, A Computer Code for Coupled Thermal-Hydraulics and FP Transport Analyses for Severe Accident at LWRs and Its Application to Analysis of FP Revaporization Phenomena.
    Proceedings of the International Topical Meeting on Safety of Thermal Reactors, Portland, pp. 584-592 (1991)

  • Hidaka, A. et. al.:
    Experimental Analysis with ART Code on FP Behaviour Under Severe Accident Conditions.
    Proceedings of Validation of Systems Transient Analysis Codes, FED, Volume 223, pp. 99-106, ASME (1995)

  • Hidaka, A., et. al.:
    Comparative Study of FP Deposition in WIND Project Piping by ART and VICTORIA.
    Proceedings of the International Conference on Probabilistic Safety Assessment Methodology and Applications, Korea (PSA '95), pp. 241-246 (1995)

  • Hidaka, A., et. al.:
    Experimental Analysis of Aerosol Behaviors in Primary Piping With ART Code During Severe Accident.
    Proceedings of the International Conference for Heat and Mass Transfer, pp. 577-587 (1996)

  • Hidaka, A. et. al.:
    Experimental Analyses of Iodine Behavior Under Severe Accident Conditions with ART.
    Journal of Nuclear Materials, Volume 248, pp. 226-232 (1997)

NEA-1581/02, included references:
- Kajimoto, M., Hidaka, A., Muramatsu, K. and Sugimoto, J.:
ART Mod 2: A Computer Code for the Analysis of Radionuclide  Transport and
Deposition under Severe Accident Conditions - Model Description and
User's Manual (Draft)
Department of Reactor Safety Research, Tokai Research  Establishment, JAERI
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11. HARDWARE REQUIREMENTS

Memory requirement is about 10 000kB.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1581/02 FORTRAN-77
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13. SOFTWARE REQUIREMENTS

Solaris CDE Version 1.0.2.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ART code is a module of JAERI's integrated severe accident analysis code, THALES-2.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Akihide HIDAKA and Jun SUGIMOTO
Japan Atomic Energy Research Institute
Severe Accident Research Laboratory
Department of Reactor Safety Research
Tokai-mura, Naka-gun, Ibaraki-ken 319-1195
JAPAN

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16. MATERIAL AVAILABLE
NEA-1581/02
artmod2r.exe                ART MOD2 executable
sample_problem_ARTmod2.doc  Description of sample Problem
wave_1hour.out              output file
wave_1hour.txt              text file
\sorce\                     source files
JW299_ART-MOD2.pdf          program abstract
electronic documentation
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, aerosols, containment systems, iodine, radionuclide migration.