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IAEA0886 INTERTRAN.

INTERTRAN-I and INTERTRAN-II, Radiation Exposure from Vehicle Transport of Radioactive Material

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1. NAME OR DESIGNATION OF PROGRAM

INTERTRAN-I and INTERTRAN-II.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
INTERTRAN-I IAEA0886/03 Tested 01-APR-1986
INTERTRAN-II IAEA0886/04 Tested 06-SEP-2002

Machines used:

Package ID Orig. computer Test computer
IAEA0886/03 Many Computers Many Computers
IAEA0886/04 IBM PC PC Pentium III 500
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3. DESCRIPTION OF PROGRAM OR FUNCTION

INTERTRAN calculates the radiological impact from incident-free shipments and from vehicular accidents involving radioactive materials. It also addresses accidents which may occur during handling. The output in the incident-free case is given as annual integrated population dose to various population subgroups from the specified primary and secondary transport mode (road, rail, air, or water). In the accident case, both early and latent health effects are analyzed in the form of early fatalities and mortalities, latent cancer fatalities, and genetic effects.

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4. METHODS

INTERTRAN is divided into a number of submodels including a standard shipment model, transportation model, accident categorization model, material dispersibility model, atmospheric dispersion model, population density model, and health effects model In the standard shipment model user-specified individual shipments of up to 80 standard materials by any of 10 different transport situations are combined so that a standard shipment consists of an average shipment of a material transported by a specified transport mode or a combination of two transport modes. The model is used to meet the code's limitation of no more than 200 different shipments per run.

 

The transportation model consists of a traffic pattern section, a shipment section, and an accident rate section. In the traffic pattern section the fraction of travel in each of three population zones (rural, suburban, and urban) is specified. These fractions are used in calculating the dose in the incident-free case and in calculating the probability of an accident occurring in the different zones. This section also contains the parameters used to determine the dose during shipment stops and the dose to persons in the vicinity of the transport link. The shipment data section deals with the parameters used to evaluate the dose to crew, handlers, passengers, and flight attendants as well as the dose received while the cargo is stored. The accident rate section calculates the accident rate depending on the severity of the accident and the population zone where it is assumed to occur. An overall accident rate and a fractional occurrence of the accident severities are specified for each transport mode. These are combined with the accident risk factors which give the fractional accident rate in a population zone to the overall accident rate for each mode, severity category, and population zone.

 

The accident categorization model contains frequencies of occurrence fordifferent accident severities in different environments. For every severity category and each of the package types a package failure fraction is determined. This fraction describes the relative degree of damage to the packages of a shipment from an accident. The probability of a certain accident is given by the overall accident rate for the actual mode, the fractional occurrence of the actual accident severity category for that mode, and the accident rate factor for the population density zone, the accident severity category, and the transport mode.

 

The material dispersibility model takes into consideration the dispersibility difference due to the chemical and physical properties of the materials shipped. Each of the eleven dispersibility categories is assigned an aerosolization factor for each accident severity category. The aerosolization factor describes the fraction of the available material which is aerosolized and readily dispersed. When combined with the package failure fraction, the aerosolization factor gives the amount of material dispersed in an accident.

 

The atmospheric dispersion model calculates the time-integrated concentration at a specific distance from the release. Isodose curves can be generated, and the amount of material deposited during the passage of the cloud and the resulting depletion of the cloud are also calculated.

 

The population density model uses three separate population zones with evenly-distributed population. They are urban or high-population density, suburban or medium-population density, and rural or low-population density. For incident-free transport by road a factor which is the ratio of pedestrian density to population density in the area is inserted. In the accident dose calculations in the urban zone the population is divided into two parts - one representing people inside buildings, the other representing people on the streets. The pedestrian density factor is applied to the population density of those on the street.

 

The health effects model analyzes early fatalities and morbidities, latent cancer fatalities, and genetic effects. In the case of dispersible materials the one-year lung and marrow doses are used to calculate the probability of an early fatality for an individual. The expected number of early mortalities is calculated by comparing the individual organ dose with a threshold value. If the dose exceeds the threshold value, the expected number of early fatalities and morbidities is the number of exposed persons. The probability of cancer developing later in life for an exposed person is assumed to be porportional to the dose. Thus, the expected number of latent cancer effects in the exposed population is calculated as the product of the population dose and the chronic effect risk factor. In the case of non-dispersible materials the whole body risk factor is used. In the case of dispersible materials the total risk is calculated as the sum of the risk to the individual organs most sensitive to radiation (lung, marrow, bone, thyroid, and gastrointestinal tract). Exposures of the gonads can induce gene mutations and chromosomal changes leading to hereditary defects. When assessing the total population detriment, a risk factor of 80*10**(-6) per person-rem for genetic effects in all subsequent generations is used.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of

  • 3 population density zones

  • 200 different shipments per run

  • 10 different package types

  • 80 material types

  • 10 transport modes

  • 11 accident severity categories

  • 30 iso-dose areas

  • 30 rem levels

  • 8 organs for dose calculation

  • 5 early fatality organs

  • 11 material dispersivity categories

  • 10 material categories

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6. TYPICAL RUNNING TIME
IAEA0886/03
  The INTERTRAN sample problem required 1 CPU seconds on an IBM3081 and about 4 CPU seconds on an IBM4331.
For running the same problems with INTERTRAN-I the following CP times were required:
                    - NAS9080(IBM-like)   0.85 seconds
                    - CDC CYBER-740      13.79 seconds
                    - VAX 11/780         12.84 seconds

IAEA0886/04
Interactive program.
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8. RELATED OR AUXILIARY PROGRAMS
IAEA0886/03
INREAD is an interactive program for generating the INTERTRAN input data file. INTERTRAN was developed by the Swedish Nuclear Power Inspectorate for the International Atomic Energy Agency. It is based on Sandia National Laboratories' RADTRAN and RADTRAN2 programs.

IAEA0886/04
The INTERTRAN2 package contains a base for risk assessment, the RADTRAN-4 computer code modified for international purposes and PC use by AMC konsult AB (www.amckonsult.se). The RADTRAN-4 mainframe computer code has been made available and modified in accordance with the recommendations of the CRP by the Sandia National Laboratories, Albuquerque, NM, USA. The INTERTRAN2 package also contains an atmospheric dispersion model made available and modified for this purpose by Institut de Protection et Surete Nucleaire (IPSN), France. The input data handler developed by the AMC Konsult AB, in Sweden under contract with the Swedish Nuclear Power Inspectorate was included after request from member states to get a tool which could facilitate for less experienced users to create their input data files for the program.

The TICLD software, included in this package, includes programming identical to a portion of RADTRAN-4 with a single additional arithmetic operation that produces an individual dose calculation for each downwind area rather than a population dose calculation. The correctness of the latter operation has been validated as part of RADTRAN 4 Software Validation and Verification activities. The program thus falls under the quality assurance umbrella of the RADTRAN 4 SQAP.  

LHS is not included in the package and has to be requested separately.

TICLD and LHS are not required for general transportation risk assessments, but are useful for more detailed analyses by experienced analysts.
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9. STATUS
Package ID Status date Status
IAEA0886/03 01-APR-1986 Tested at NEADB
IAEA0886/04 06-SEP-2002 Tested at NEADB
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10. REFERENCES
  • INTERTRAN, NESC No. I886.3081, INTERTRAN Tape Description and Implementation Information, National Energy Software Center Note 85-63, April 25, 1985.

IAEA0886/03, included references:
- A.M. Ericsson and M. Elert:
  INTERTRAN: A System for Assessing the Impact from Transporting
  Radioactive Material.  IAEA-TECDOC-287  (May 1983), revised by
  NEADB (INTERTRAN-I)  (March 1986).
- G.B. Pettersson:
  Chairman's Report of the Technical Committee on the Assessment of
  the Radiological Impact from the Transport of Radioactive
  Materials
  IAEA-TC-556 Vienna, 21-25 October 1985.
- Y. Yamaguchi and E. Sartori:
  Improved Maintenance and Portability in a Generalized Version of
  the INTERTRAN Computer Code.
  OECD/NEADB Internal Report
- T.A. Mehlhorn and M.F. Young:
  UPEML - A Machine-Portable CDC Update Emulator
  SAND84-1896  (December 1984)
IAEA0886/04, included references:
- A-M Ericsson, C. Jarnry:
INTERTRAN2 Transportation Risk Assessment Package, User's Guide
- J-P. Degrange, A-M Ericsson, C. Jarnry, T.F Kempe, S. Neuhauser, H. Wilkinson:
ADVISORY MATERIAL for the INTERTRAN2 computer program.
- Ann-Margret Ericsson, Clifford Jarnry:
INTERTRAN2 Transportation Risk Assessment Package Training Course
Documentation
- INTERTRAN2 cases for the IAEA Training Course
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11. HARDWARE REQUIREMENTS
IAEA0886/03
284K bytes on a NAS 9080
140K octal words on CDC CYBER-740
603 peak page size (300k bytes) on VAX-11/780

IAEA0886/04
PC computer. The handler is developed using CA-Visual Objects, a 32-bit fully object oriented language.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0886/03 FORTRAN-77
IAEA0886/04 FORTRAN-90
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13. SOFTWARE REQUIREMENTS
IAEA0886/03
MVS-SP (IBM3081,  4331). NOS (CDC CYBER-740), VMS (VAX-11/780), MVS-XA (NAS9080).

IAEA0886/04
Windows 95/98/2000 and NT.
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15. NAME AND ESTABLISHMENT OF AUTHORS
IAEA0886/03
          Dagmar M. Pal
          Radiological Safety Section
          Division of Nuclear Safety
          I.A.E.A.
          P.O.B. 100
          A-1400 Vienna, Austria

IAEA0886/04
Developed by:
    AMC Konsult
    Abrahamsbergsv. 89
    S-16830 Bromma
    Sweden

under contract from the Swedish Nuclear Power Inspectorate
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16. MATERIAL AVAILABLE
IAEA0886/04
Libraries, Data, Executables,Help and Installation files for Intertran-II
Databases for the IAEA training course
TICLD material
AdvisoryMaterial.pdf Documentation
UsersGuide.pdf Documentation
Documentation of the IAEA training course
IAEA0886/03
File name File description Records
IAEA0886_03.001 INTERTRAN-I Information file 177
IAEA0886_03.002 INTERTRAN-I Source program in UPDATE format 3907
IAEA0886_03.003 INTERTRAN-I Source program IBM version 4142
IAEA0886_03.004 INREAD Source program in UPDATE format 1384
IAEA0886_03.005 INREAD Source program IBM version 1388
IAEA0886_03.006 UPEML Source program(FORTRAN-V) 2577
IAEA0886_03.007 TRUNCATE Source program(FORTRAN-V) 39
IAEA0886_03.008 INTERTRAN-I Job Control Instructions for IBM 120
IAEA0886_03.009 INTERTRAN-I Job Control Instructions for CDC 54
IAEA0886_03.010 INTERTRAN-I Job Control Instructions for VAX 55
IAEA0886_03.011 INTERTRAN-I Sample case input 55
IAEA0886_03.012 INTERTRAN-I Printed output for sample case 1967
IAEA0886_03.013 UPEML Printed output 56
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, dispersions, doses, human populations, inhalation, organs, radioactivity transport, risk assessment.