Energi- och värmeöverföring

This document sets the basic principles for determination of groundwater remediation target value for uranium in-situ leaching, the environmental investigation requirements for uranium in-situ leaching, groundwater remediation technology and economic-benefit analysis, and the procedure for determination of groundwater remediation target value This document is applicable to control and remediation of groundwater impact of uranium in-situ leaching.

This International Standard provides a methodology to estimate a reasonably maximal value of the number of fissions of a postulated criticality accident. The fission number estimate, associated with its postulated criticality accident, impacts the accident emergency planning and response because it is used for the estimation of radiation doses and of radioactive materials release. This International Standard does not provide a methodology and guidance to determine bounding accident scenarios. This International Standard does not cover criticality accident detection which is dealt with by ISO 7753. This International Standard does apply to nuclear facilities, plants, laboratories, storage, and transportation of fissile material (but not to nuclear power reactor cores) where a credible criticality accident may occur.

This document describes the procedures to prepare plutonium sources and to measure the activity ratio of 238Pu to (239Pu + 240Pu) by alpha spectrometry. The alpha spectrometry method is used for the determination of isotopic abundance of 238Pu in combination with isotope amount ratios determined by mass spectrometry and eliminates the possible isobaric interferences of 238U in the latter method. It is applied to the analysis of purified solutions of plutonium in 2 mol/l to 4 mol/l nitric acid containing 50 µg to 200 µg of plutonium per millilitre, as may result from the chemical treatment and purification preceding plutonium isotopic analysis by mass spectrometry.

This document is applied to plutonium solutions free from 241Am and those containing less than 10 % of other non-volatile impurities relative to the plutonium content. Otherwise purification should be carried out in accordance with ISO 8299.

The methods provided in this document are intended for use in conjunction or in parallel with mass spectrometry for the isotopic analysis of plutonium in spent-fuel solutions or nuclear-grade plutonium products.

The scope of this proposal is to establish a methodology and analytical framework to determine the GHG emissions related to a unit of hydrogen converted and transported via liquid organic hydrogen carriers up to the consumption gate.

This document provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity. NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production. The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs). This document also provides a procedure for evaluating neutron damage properties at the reactor pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons and indirect damage caused by gas production, both of which are strongly dependent on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of the total accumulated number of atomic displacements are important data to be used for reactor life management.

This document is applicable to fuel fabrication. It gives guidelines on the determination of the specific surface area of as-fabricated uranium dioxide and plutonium dioxide powders by volumetric or gravimetric determination of the amount of nitrogen adsorbed on the powder. The measurement of other uranium oxide powders refers to uranium dioxide, such as UO3 and U3O8. The measurement of MOX(UO2-PuO2) powders refers to plutonium dioxide. When conditions described are fulfilled, modifications using other adsorbing gases are included.

The method is relevant as long as the expected value is in the range from 1 m2/g to 10 m2/g for uranium dioxide powders, in the range from 0.1 m2/g to 45 m2/g for plutonium dioxide powders.