Energi- och värmeöverföring

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.

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

The scope of this proposal is to establish a methodology and analytical framework to determine the GHG emissions related to the production and transport of Ammonia up to the consumption gate and related to the conversion of Ammonia into hydrogen and its transport to consumption gate.

This document defines the minimum requirements to ensure the interoperability of hydrogen refuelling points, including refuelling protocols that dispense liquid hydrogen to road vehicles that comply with legislation applicable to such vehicles. This document focuses on heavy-duty vehicles as defined in Regulation (EU) 2023/1804. The safety and performance requirements for the entire hydrogen fuelling station, addressed in accordance with existing relevant European and national legislation, are not included in this document. This document applies to hydrogen refuelling points and dispensing systems providing liquid hydrogen to vehicles compliant with Regulation (EU) 2019/2144. NOTE Guidance on considerations for hydrogen fuelling stations is provided in ISO 13984:-.

This document specifies design criteria for heating and cooling systems in buildings using electrically driven heat pumps for heating and cooling alone or in combination with other heat generators. The heat pump systems considered in this document (source system/sink system) are listed in Table 1. For cooling purposes, energy source and energy sink can be reversed. This document also applies to other energy sources such as wastewater, massive absorbers, ice storage systems, as well as heat pump systems using more than one energy source. This document takes into account the heating requirements of attached systems (e.g. domestic hot water) in the design of the heat supply but does not cover the design of these systems. This document covers the aspects dealing with the heat pump, the interface with the heat distribution system and heat emission system, the control of the whole system and the aspects dealing with energy source of the system. Design criteria for reversible heat pump systems for heating and cooling are also included in this document. Table 1 - Heat pump systems used for heating (within the scope)

This International Standard establishes an evaluation methodology for nuclear criticality safety with burnup credit. It identifies important parameters and specifies requirements, recommendations, and precautions to be taken into account in the evaluations. It also highlights the main important technical fields to ensure that the fuel composition or history considered in calculations provides a bounding value of the effective neutron multiplication factor, keff. A more practical approach is also presented.

This International Standard is applicable to transport, storage, disposal or reprocessing units implying irradiated fissile material from pressurized water reactor (PWR) fuels that initially contain enriched uranium oxide (UOX). Uranium could originate either from natural uranium or recycled uranium.

Fuels irradiated in other reactors (e.g. boiling water reactors) and fuels that initially contain mixed uranium-plutonium oxide are not covered in this International Standard.

This International Standard does not specify requirements related to overall criticality safety evaluation or eventual implementation of burnup credit.