International Conference on the Safety of Radioactive Waste Management, Decommissioning, Environmental Protection and Remediation: Ensuring Safety and Enabling Sustainability

Comparative study for Inventory Estimation for Halden BWR Spent Fuel

Not scheduled

20m

M-Building (IAEA Headquarters, Vienna)

POSTER Track 6 - Building capacity for ensuring safety and enabling sustainability

Speaker

Sabina Maharramova (Institute of Radiation Problems)

Description

The paper presents theoretical and experimental results of
investigation of the possibility of using nondestructive gamma-ray spectroscopy to estimate long-lived radionuclide inventories of Halden BWR spent fuel. An accurate estimation of long-lived actinides and fission products inventories are important for long-term safety analysis, as well as to account the radiological impacts on the public and the environment.
The study has been performed at the Halden Boiling Water Reactor in Halden, Norway. The five rods fuel assembly with burnup of 50.6 MWd/kgUO2 is selected for this study. All the data for the theoretical study is generated using SCALE-6.2.2 codes system and ENDF/B-VII.0 nuclear data library. 972 computational data sets are made by variations of various operational parameters and 80 gamma measurements of photon-emitting caesium nuclides are analyzed for the study.
The 134Cs/137Cs ratio is used for the radionuclide inventory estimation of Halden spent fuel with real power history, by comparing gamma scan
isotope ratios to the calculated actinide and fission product
inventories. Preliminary results of the comparison have shown that 38 of
972 and 79 of 972 data sets are within ±5% and ±10% of the measured
value of the 134Cs/137Cs ratio.