1. NAME AND TITLE
PURSE: A Plutonium Radiation Source Code System.
Power Reactor and Nuclear Fuel Development Corporation, Tokai-mura Ibaraki-ken, Japan.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; CDC-6600.
4. NATURE OF PROBLEM SOLVED
PURSE calculates alpha-, beta-, and gamma-rays and neutron intensity from fresh plutonium
mixed-oxide fuels which contain daughter nuclides of plutonium and uranium. PURSE can also
calculate gamma-ray spectra from mixed-oxide fuels.
5. METHOD OF SOLUTION
Four main decay chains of uranium, actinium, thorium and neptunium are considered. In addition, the decay chains of transplutonium elements and some types of fission product elements, which remain in plutonium in trace amounts after reprocessing, are considered.
The activity in curies and the emission energy of the alpha-, beta-, and gamma-rays from the
nuclides in these decay chains are calculated as a function of time. Up to 18 gamma-ray energy groups
can be taken, the total and average energy of each group can be calculated, and the gamma-ray
spectrum is plotted with the use of a plotter. The neutrons from spontaneous fission and (alpha,n)
reactions with oxygen are considered.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
The running time for PURSE is approximately one minute.
8. COMPUTER HARDWARE REQUIREMENTS
PURSE was designed to run on the CDC 6600. The plotter used is the CalComp 915-1136.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
R. Yumoto, H. Sasajima, and S. Fukuda, "PURSE: A Plutonium Radiation Source Code," PNCT
852-78-13 (October 1978).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
codes and sample problem input.
12. DATE OF ABSTRACT
KEYWORDS: PLUTONIUM; GAMMA-RAY SOURCE; ISOTOPE INVENTORY; ACTINIDES; FUEL-HANDLING FACILITIES