GET https://dev.normadoc.fr/_partial/product/IEEE00006483/features

Components

4 Twig Components
18 Render Count
13 ms Render Time
294.0 MiB Memory Usage

Components

Name Metadata Render Count Render Time
ProductState
"App\Twig\Components\ProductState"
components/ProductState.html.twig
8 1.56ms
ProductMostRecent
"App\Twig\Components\ProductMostRecent"
components/ProductMostRecent.html.twig
8 5.43ms
ProductType
"App\Twig\Components\ProductType"
components/ProductType.html.twig
1 0.18ms
ProductCard
"App\Twig\Components\ProductCard"
components/ProductCard.html.twig
1 6.94ms

Render calls

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          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.
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App\Twig\Components\ProductState {#106972
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      date: 1978-09-14 00:00:00.0 Europe/Paris (+02:00)
    }
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    }
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    -bookCollection: ""
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    -documents: Doctrine\ORM\PersistentCollection {#129030 …}
    -favorites: Doctrine\ORM\PersistentCollection {#129028 …}
  }
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  +labels: [
    "Withdrawn"
  ]
  -stateAttributeCode: "state"
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}
ProductMostRecent App\Twig\Components\ProductMostRecent 294.0 MiB 0.64 ms
Input props
[
  "product" => App\Entity\Product\Product {#129035
    #id: 8437
    #code: "IEEE00000469"
    #attributes: Doctrine\ORM\PersistentCollection {#129015 …}
    #variants: Doctrine\ORM\PersistentCollection {#129013 …}
    #options: Doctrine\ORM\PersistentCollection {#129008 …}
    #associations: Doctrine\ORM\PersistentCollection {#129010 …}
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      date: 2025-06-27 17:16:55.0 Europe/Paris (+02:00)
    }
    #updatedAt: DateTime @1754606304 {#128999
      date: 2025-08-08 00:38:24.0 Europe/Paris (+02:00)
    }
    #enabled: true
    #translations: Doctrine\ORM\PersistentCollection {#129026 …}
    #translationsCache: [
      "en_US" => App\Entity\Product\ProductTranslation {#129119
        #locale: "en_US"
        #translatable: App\Entity\Product\Product {#129035}
        #id: 28757
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        #description: """
          New IEEE Standard - Inactive-Withdrawn.<br />\n
          These criteria established minimum requirements for the safety-related functional performance and reliability of protection systems for stationary land-based nuclear reactors producing steam for electric power generation. Fulfillment of these requirements does not necessarily fully establish the adequacy of protective system functional performance and reliability. On the other hand, omission of any of these requirements will, in most instances, be an indication of system inadequacy. For purposes of these criteria, the nuclear power generating station protection system encompasses all electric and mechanical devices and circuitry (from sensors to actuation device input terminals) involved in generating those signals associated with the protective function. These signals include those that actuate reactor trip and that, in the event of a serious reactor accident, actuate engineered safeguards such as containment isolation, core spray, safety injection, pressure reduction, and air cleaning.<br />\n
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        #shortDescription: "IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations"
        -notes: "Inactive-Withdrawn"
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    #productTaxons: Doctrine\ORM\PersistentCollection {#129023 …}
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    #reviews: Doctrine\ORM\PersistentCollection {#129021 …}
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    -author: ""
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]
Attributes
[]
Component
App\Twig\Components\ProductMostRecent {#129201
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    }
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        #translatable: App\Entity\Product\Product {#129035}
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          New IEEE Standard - Inactive-Withdrawn.<br />\n
          These criteria established minimum requirements for the safety-related functional performance and reliability of protection systems for stationary land-based nuclear reactors producing steam for electric power generation. Fulfillment of these requirements does not necessarily fully establish the adequacy of protective system functional performance and reliability. On the other hand, omission of any of these requirements will, in most instances, be an indication of system inadequacy. For purposes of these criteria, the nuclear power generating station protection system encompasses all electric and mechanical devices and circuitry (from sensors to actuation device input terminals) involved in generating those signals associated with the protective function. These signals include those that actuate reactor trip and that, in the event of a serious reactor accident, actuate engineered safeguards such as containment isolation, core spray, safety injection, pressure reduction, and air cleaning.<br />\n
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          """
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    #fallbackLocale: "en_US"
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    -supplier: Proxies\__CG__\App\Entity\Supplier\Supplier {#7325 …}
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    -documents: Doctrine\ORM\PersistentCollection {#129030 …}
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  }
  +label: "Most Recent"
  +icon: "check-xs"
  -mostRecentAttributeCode: "most_recent"
  -localeContext: Sylius\Component\Locale\Context\CompositeLocaleContext {#1833 …}
}