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Released: 06.02.2023
IEEE 535-2022 - IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations
IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations
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Standard number: | IEEE 535-2022 |
Released: | 06.02.2023 |
ISBN: | 978-1-5044-9277-5 |
Pages: | 27 |
Status: | Active |
Language: | English |
DESCRIPTION
IEEE 535-2022
This standard describes qualification methods for Class 1E vented lead-acid batteries and racks to be used in nuclear power generating stations outside primary containment. Qualifications required by IEEE Std 308 can be demonstrated by using the procedures in this standard in accordance with IEC/IEEE 60780-323. Application of batteries in nuclear power generating stations can be divided into two sections: duty cycles equal to or less than 8 h and duty cycles greater than 8 h. This standard provides a process to demonstrate qualification for both applications. This standard is based on the user demonstrating that the predominant failure mechanism is positive plate grid corrosion. The following technologies have been demonstrated to meet this criterion for full float service: a) Lead-calcium b) Lead-antimony c) Lead-selenium (low-antimony) To apply this standard to vented lead-acid technologies other than those listed above, the user is required to demonstrate the following for full float service: a) The predominant failure mechanism is positive plate grid corrosion using either natural aging or accelerated aging using aging factors specific to the technology. Battery sizing, maintenance, capacity testing, installation, charging equipment, and consideration of other battery technologies are beyond the scope of this standard.Revision Standard - Active. Qualification methods for Class 1E vented lead acid batteries and racks to be used in nuclear power generating stations outside primary containment are described in this standard. Qualifications required by IEEE Std 308 can be demonstrated by using the procedures in this standard in accordance with IEEE Std 323. The application of batteries in nuclear power generating stations can be divided into two sections: duty cycles equal to or less than 8 h and duty cycles greater than 8 h. A process to demonstrate qualifications for both applications is provided in this standard