GET https://dev.normadoc.fr/_partial/cart/summary?template=%40SyliusShop%2FCart%2F_widget.html.twig

Response
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216.73.216.116
Profiled on
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Components

4 Twig Components
18 Render Count
17 ms Render Time
102.0 MiB Memory Usage

Components

Name Metadata Render Count Render Time
ProductState 
"App\Twig\Components\ProductState"
components/ProductState.html.twig 		8 1.72ms
ProductMostRecent 
"App\Twig\Components\ProductMostRecent"
components/ProductMostRecent.html.twig 		8 5.73ms
ProductType 
"App\Twig\Components\ProductType"
components/ProductType.html.twig 		1 0.22ms
ProductCard 
"App\Twig\Components\ProductCard"
components/ProductCard.html.twig 		1 10.18ms

Render calls

ProductState App\Twig\Components\ProductState 68.0 MiB 0.32 ms
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        #description: """
           - Superseded.<br />\n
          <br />\n
          \t\t\t\t<br />\n
          This document describes qualification methods for Class IE lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1971 [1] and IEEE Std 308-1978, [2] can be demonstrated by using the procedures provided in this standard in accordance with IEEE Std 323-1974, [3] . Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other type batteries are beyond the scope of this standard.
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Component 
App\Twig\Components\ProductState {#92876
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        #id: 41901
        #name: "IEEE 535:1979"
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        #description: """
           - Superseded.<br />\n
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          This document describes qualification methods for Class IE lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1971 [1] and IEEE Std 308-1978, [2] can be demonstrated by using the procedures provided in this standard in accordance with IEEE Std 323-1974, [3] . Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other type batteries are beyond the scope of this standard.
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ProductType App\Twig\Components\ProductType 68.0 MiB 0.22 ms
Input props 
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    #id: 11723
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    #enabled: true
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        #locale: "en_US"
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           - Superseded.<br />\n
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Attributes 
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Component 
App\Twig\Components\ProductType {#93056
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        #description: """
           - Superseded.<br />\n
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}
ProductMostRecent App\Twig\Components\ProductMostRecent 68.0 MiB 0.69 ms
Input props 
[
  "product" => App\Entity\Product\Product {#7310
    #id: 11723
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    #enabled: true
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        #name: "IEEE 535:1979"
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           - Superseded.<br />\n
          <br />\n
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          This document describes qualification methods for Class IE lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1971 [1] and IEEE Std 308-1978, [2] can be demonstrated by using the procedures provided in this standard in accordance with IEEE Std 323-1974, [3] . Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other type batteries are beyond the scope of this standard.
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Component 
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           - Superseded.<br />\n
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ProductState App\Twig\Components\ProductState 82.0 MiB 0.20 ms
Input props 
[
  "product" => App\Entity\Product\Product {#93554
    #id: 12447
    #code: "IEEE00007706"
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        #description: """
          Revision Standard - Active.<br />\n
          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<br />\n
          \t\t\t\t<br />\n
          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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        #metaKeywords: null
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        #shortDescription: "IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations"
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Attributes 
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]
Component 
App\Twig\Components\ProductState {#106841
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ProductMostRecent App\Twig\Components\ProductMostRecent 82.0 MiB 0.67 ms
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Input props 
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ProductState App\Twig\Components\ProductState 102.0 MiB 0.24 ms
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      date: 1978-09-14 00:00:00.0 Europe/Paris (+02:00)
    }
    -canceledAt: DateTime @456012000 {#129061
      date: 1984-06-14 00:00:00.0 Europe/Paris (+02:00)
    }
    -edition: null
    -coreDocument: "279"
    -bookCollection: ""
    -pageCount: 12
    -documents: Doctrine\ORM\PersistentCollection {#129058 …}
    -favorites: Doctrine\ORM\PersistentCollection {#129056 …}
  }
  +appearance: "state-withdrawn"
  +labels: [
    "Withdrawn"
  ]
  -stateAttributeCode: "state"
  -localeContext: Sylius\Component\Locale\Context\CompositeLocaleContext {#1833 …}
}
ProductMostRecent App\Twig\Components\ProductMostRecent 102.0 MiB 0.93 ms
Input props 
[
  "product" => App\Entity\Product\Product {#129063
    #id: 8437
    #code: "IEEE00000469"
    #attributes: Doctrine\ORM\PersistentCollection {#129043 …}
    #variants: Doctrine\ORM\PersistentCollection {#129041 …}
    #options: Doctrine\ORM\PersistentCollection {#129036 …}
    #associations: Doctrine\ORM\PersistentCollection {#129038 …}
    #createdAt: DateTime @1751037415 {#129034
      date: 2025-06-27 17:16:55.0 Europe/Paris (+02:00)
    }
    #updatedAt: DateTime @1754606304 {#129027
      date: 2025-08-08 00:38:24.0 Europe/Paris (+02:00)
    }
    #enabled: true
    #translations: Doctrine\ORM\PersistentCollection {#129054 …}
    #translationsCache: [
      "en_US" => App\Entity\Product\ProductTranslation {#129147
        #locale: "en_US"
        #translatable: App\Entity\Product\Product {#129063}
        #id: 28757
        #name: "IEEE 279:1971 (R1978)"
        #slug: "ieee-279-1971-r1978-ieee00000469-240089"
        #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
          \t\t\t\t
          """
        #metaKeywords: null
        #metaDescription: null
        #shortDescription: "IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations"
        -notes: "Inactive-Withdrawn"
      }
    ]
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    #currentTranslation: null
    #fallbackLocale: "en_US"
    #variantSelectionMethod: "match"
    #productTaxons: Doctrine\ORM\PersistentCollection {#129051 …}
    #channels: Doctrine\ORM\PersistentCollection {#129045 …}
    #mainTaxon: Proxies\__CG__\App\Entity\Taxonomy\Taxon {#7311 …}
    #reviews: Doctrine\ORM\PersistentCollection {#129049 …}
    #averageRating: 0.0
    #images: Doctrine\ORM\PersistentCollection {#129047 …}
    -supplier: Proxies\__CG__\App\Entity\Supplier\Supplier {#7325 …}
    -subscriptionCollections: Doctrine\ORM\PersistentCollection {#129060 …}
    -apiLastModifiedAt: DateTime @1754517600 {#129020
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    }
    -author: ""
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    }
    -releasedAt: null
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]
Attributes 
[]
Component 
App\Twig\Components\ProductMostRecent {#129229
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    #id: 8437
    #code: "IEEE00000469"
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    #variants: Doctrine\ORM\PersistentCollection {#129041 …}
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    }
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    }
    #enabled: true
    #translations: Doctrine\ORM\PersistentCollection {#129054 …}
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      "en_US" => App\Entity\Product\ProductTranslation {#129147
        #locale: "en_US"
        #translatable: App\Entity\Product\Product {#129063}
        #id: 28757
        #name: "IEEE 279:1971 (R1978)"
        #slug: "ieee-279-1971-r1978-ieee00000469-240089"
        #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
          \t\t\t\t
          """
        #metaKeywords: null
        #metaDescription: null
        #shortDescription: "IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations"
        -notes: "Inactive-Withdrawn"
      }
    ]
    #currentLocale: "en_US"
    #currentTranslation: null
    #fallbackLocale: "en_US"
    #variantSelectionMethod: "match"
    #productTaxons: Doctrine\ORM\PersistentCollection {#129051 …}
    #channels: Doctrine\ORM\PersistentCollection {#129045 …}
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    #reviews: Doctrine\ORM\PersistentCollection {#129049 …}
    #averageRating: 0.0
    #images: Doctrine\ORM\PersistentCollection {#129047 …}
    -supplier: Proxies\__CG__\App\Entity\Supplier\Supplier {#7325 …}
    -subscriptionCollections: Doctrine\ORM\PersistentCollection {#129060 …}
    -apiLastModifiedAt: DateTime @1754517600 {#129020
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    }
    -lastUpdatedAt: DateTime @1578006000 {#129069
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    }
    -author: ""
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      date: 1970-11-30 00:00:00.0 Europe/Paris (+01:00)
    }
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      date: 1978-09-14 00:00:00.0 Europe/Paris (+02:00)
    }
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      date: 1984-06-14 00:00:00.0 Europe/Paris (+02:00)
    }
    -edition: null
    -coreDocument: "279"
    -bookCollection: ""
    -pageCount: 12
    -documents: Doctrine\ORM\PersistentCollection {#129058 …}
    -favorites: Doctrine\ORM\PersistentCollection {#129056 …}
  }
  +label: "Most Recent"
  +icon: "check-xs"
  -mostRecentAttributeCode: "most_recent"
  -localeContext: Sylius\Component\Locale\Context\CompositeLocaleContext {#1833 …}
}