1. NAME AND TITLE

PIEDEC: A Practical Internal Exposure Dose Evaluation Code.

2. CONTRIBUTOR

Kansai Electric Power Company and Mitsubishi Atomic Power Industries Inc., Japan, through the NEA Data Bank, France.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; IBM 3083, FACOM-M380.

4. NATURE OF PROBLEM SOLVED

PIEDEC calculates the initial intake activity and effective dose equivalent of a worker (who ingests radioactive nuclides by inhalation or oral intake) using measured data (whole-body counting or bioassay test).

5. METHOD OF SOLUTION

The transformation of radioactive nuclides in each source organ is calculated by integration of the analytically solved retention function using the Gauss-Legendre method. The effective dose equivalent is obtained from multiplying specific energies and the transformations. The input for gamma-ray emitters is the internal contamination measured by the whole-body counter; for alpha- and beta-ray emitters it is the activity in urine or faeces. The code contains two sections: initial intake activity evaluation and dose equivalent evaluation. The first applies the retention functions of the total body to gamma-ray emitters and excretion functions to alpha- and beta-ray emitters. The excretion functions have been obtained from the excretion models as prepared in this study.

6. RESTRICTIONS OR LIMITATIONS

The code is restricted to 14 radionuclides.

7. TYPICAL RUNNING TIME

The sample input was tested on the IBM 3083 at NEA Data Bank. It took 125.57 seconds.

8. COMPUTER HARDWARE REQUIREMENTS

PIEDEC runs on the IBM 3083 and FACOM-M380.

9. COMPUTER SOFTWARE REQUIREMENTS

The code was written in Fortran 77. On the IBM 3083, the compiler used was VS Fortran Level 2.1.1.

10. REFERENCES

a. Included in the documentation:

"PIEDEC, A Practical Internal Exposure Dose Evaluation Code," NEA 1084 (January 20, 1989).

b. Background information:

S. Iwai, K. Tanaka, A. Ikeoka, T. Mimura and K. Matsutani, "Practical Internal Dose Evaluation Based on ICRP 30 Model IAEA-SM-276/07," pp. 459-473 in Proc. International Symposium on the Assessment of Radioactive Contamination in Man, (1984) IAEA, Vienna.

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2 MB) DOS diskette.

12. DATE OF ABSTRACT

December 1990.