The FORTRAN program SPECT has been written for use in a radioisotope quality control environment to process gamma ray spectra for the estimation of specific impurities in a radiopharmaceutical product. The analysis is performed using a radionuclide library containing details of the principal radioisotopes, expected impurities and known spectrum artifacts. The program provides a plot of the spectrum on which significant peaks are marked. The activities of identified radioisotopes are calculated from principal emission and decay data contained in the library. The program output lists these activities, together with artifact peaks of known origin and details of unidentified peaks. Comments to assist the user are also provided. Since the progra...
International audienceHigh resolution gamma-ray spectrometry is a well-established metrological tech...
Summary. The types of nuclear data and their quality required in the production and application of d...
International audienceThis paper presents the progress of an ongoing study within Working Group N°27...
The FORTRAN program IMPURE is used to process the gamma spectrum of 99mTc eluted from fission produc...
A plutonium gamma-ray analysis system that operates on MS-DOS-based computers has been developed for...
Gamma radiation is electromagnetic radiation from the radioactive decay of atomic nuclei. Gamma spec...
Due to the character of the original source materials and the nature of batch digitization, quality ...
A computer code, called GAMIDENT, was written to help identify isotopes by their gamma-ray emissions...
STATEFIT is a program written in Fortran IV for the IBM 370/195 computer to facilitate the interpret...
The Nuclear Safeguards Program at the Los Alamos National Laboratory has developed and fielded techn...
This report describes the development history and characteristics of software developed in the Safeg...
The radionuclide purity of a radiopharmaceutical product is usually measured by gamma-ray spectrome...
Non-destructive gamma-ray analysis is a fundamental part of nuclear safeguards, including nuclear en...
Determination of the spatial distribution and quantification of concentration of pure beta- and phot...
Qualitative and quantitative analysis of samples require good judgment from the analysts. These two ...
International audienceHigh resolution gamma-ray spectrometry is a well-established metrological tech...
Summary. The types of nuclear data and their quality required in the production and application of d...
International audienceThis paper presents the progress of an ongoing study within Working Group N°27...
The FORTRAN program IMPURE is used to process the gamma spectrum of 99mTc eluted from fission produc...
A plutonium gamma-ray analysis system that operates on MS-DOS-based computers has been developed for...
Gamma radiation is electromagnetic radiation from the radioactive decay of atomic nuclei. Gamma spec...
Due to the character of the original source materials and the nature of batch digitization, quality ...
A computer code, called GAMIDENT, was written to help identify isotopes by their gamma-ray emissions...
STATEFIT is a program written in Fortran IV for the IBM 370/195 computer to facilitate the interpret...
The Nuclear Safeguards Program at the Los Alamos National Laboratory has developed and fielded techn...
This report describes the development history and characteristics of software developed in the Safeg...
The radionuclide purity of a radiopharmaceutical product is usually measured by gamma-ray spectrome...
Non-destructive gamma-ray analysis is a fundamental part of nuclear safeguards, including nuclear en...
Determination of the spatial distribution and quantification of concentration of pure beta- and phot...
Qualitative and quantitative analysis of samples require good judgment from the analysts. These two ...
International audienceHigh resolution gamma-ray spectrometry is a well-established metrological tech...
Summary. The types of nuclear data and their quality required in the production and application of d...
International audienceThis paper presents the progress of an ongoing study within Working Group N°27...