Comparison of various hours living fission products for absolute power density determination in VVER-1000 mock up in LR-0 reactor

Košťál, Michal; Švadlenková, Marie; Koleška, Michal; Rypar, Vojtěch; Milčák, Ján

doi:10.1016/j.apradiso.2015.08.037

Cited by 5 publications

(1 citation statement)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A suitable method for power distribution determination in the reactor core based on measurement and analysis of the short-living fission products in lightly irradiated fuel pins has been developed on the experimental facility for gamma scanning at the LR-0 experimental reactor [2][3][4]. The analysis of fuel rod failure character is the key to a real-time detection system for fuel rod failure in a pressurized water reactor (PWR) of great significance for the safe operation of nuclear reactors [5,6].…”

Section: Introductionmentioning

confidence: 99%

Fission Product Release From High and Low-Enriched Uranium Fuels of the IVG.1M Research Reactor

Medetbekov B.S.

2023

Eurasian phys. tech. j.

View full text Add to dashboard Cite

The research involved conducting resource tests on two experimental water-cooled technological channels (WCTCs) utilizing low-enriched uranium (LEU) fuel within the IVG1.M research reactor. This testing was a crucial step in the reactor's conversion from highly enriched uranium (HEU) fuel to LEU. The research focused on two key parameters, namely the specific activity and the relative release of fission products (FPs) into the coolant, to evaluate the tightnessof the fuel element cladding.A gamma-spectrometric sampling method was proposed to determine the relative releaseof FPs, which involved assessing the specific activity of the coolant, calculating the release rate (Release), the born rate (Born), and the R/B ratio of FPs. Comparative gamma-spectrometric measurements were conducted to analyze the content of FPs and activation products (AP) in the coolant of WCTCs utilizing both LEU and HEU during the tests.From the comprehensive list of detected radionuclides in the IVG.1M reactor coolant, well-identified reference radionuclides recommended for monitoringfuel element cladding tightness were carefully selected. The results of the study provided insights into the specific activity and relative release of FPs, demonstrating that quantitative values for the relative release of FPs from WCTCs using LEU and HEU fuel were comparable.

show abstract