Below is a listing of projects past and present carried out by the Saint Lucia Bureau of Standards.
Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material
60.60 Standard published
Validation of the strength of reference solutions used for measuring concentrations
90.93 Standard confirmed
Nuclear fuel technology — Determination of uranium in reprocessing-plant dissolver solution — Liquid chromatography method
90.60 Close of review
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
90.93 Standard confirmed
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors — Amendment 1: Corrections and clarifications
60.00 Standard under publication
Nuclear criticality safety — Emergency preparedness and response
90.93 Standard confirmed
Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant
90.60 Close of review
Nuclear fuel technology — Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
90.93 Standard confirmed
Nuclear fuel technology — Controlled-potential coulometric assay of plutonium
90.92 Standard to be revised
Nuclear fuel technology — Uranium dioxide powder and pellets — Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction
90.60 Close of review
Nuclear energy — Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets — Inert gas extraction and conductivity detection method
90.60 Close of review
Nuclear fuel technology — Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method
90.93 Standard confirmed
Representative sampling of plutonium nitrate solutions for determination of plutonium concentration
90.93 Standard confirmed
Safe transport of radioactive materials — Leakage testing on packages
60.60 Standard published
Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel — Guidelines to help in the definition of a product specification
90.60 Close of review
Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants — Combined method using K-absorption edge and X-ray fluorescence spectrometry
90.60 Close of review
Nuclear energy — Nuclear fuel technology — Determination of neptunium in nitric acid solutions by spectrophotometry
90.60 Close of review
Nuclear fuel technology — Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography — Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range
90.93 Standard confirmed