On-site gamma-ray spectroscopic measurements of fission gas release in irradiated nuclear fuel.
An experimental, non-destructive in-pool, method for measuring fission gas release (FGR) in irradiated nuclear fuel has been developed. Using the method, a significant number of experiments have been performed in-pool at several nuclear power plants of the BWR type. The method utilises the 514 keV gamma-radiation from the gaseous fission product (85)Kr captured in the fuel rod plenum volume. A submergible measuring device (LOKET) consisting of an HPGe-detector and a collimator system was utilised allowing for single rod measurements on virtually all types of BWR fuel. A FGR database covering a wide range of burn-ups (up to average rod burn-up well above 60 MWd/kgU), irradiation history, fuel rod position in cross section and fuel designs has been compiled and used for computer code benchmarking, fuel performance analysis and feedback to reactor operators. Measurements clearly indicate the low FGR in more modern fuel designs in comparison to older fuel types.
Matsson
I
I
Department of Nuclear and Particle Physics, Uppsala University, Box 535, S 751 21 Uppsala, Sweden. ingvar.matsson@seb.se
Grapengiesser
B
B
Andersson
B
B
D005740:Gases / Q000032:analysis; D007727:Krypton Radioisotopes / Q000032:analysis*; D009680:Nuclear Fission; D009688:Nuclear Reactors; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods*; D015203:Reproducibility of Results; D012680:Sensitivity and Specificity; D013051:Spectrometry, Gamma / Q000379:methods*; D017974:Uranium Compounds / Q000032:analysis* / Q000528:radiation effects*
D005740:Gases; D007727:Krypton Radioisotopes; D017974:Uranium Compounds; C047385:uranium oxide