Rules for Inservice Inspection of Nuclear Power Plant Components
E12784
Rules for Inservice Inspection of Nuclear Power Plant Components is a key section of the ASME Boiler and Pressure Vessel Code that establishes requirements for the periodic examination, testing, and maintenance of nuclear power plant components to ensure their continued safety and integrity.
All labels observed (3)
| Label | Occurrences |
|---|---|
| ASME Section XI | 2 |
| ASME BPVC Section XII | 1 |
| Rules for Inservice Inspection of Nuclear Power Plant Components canonical | 1 |
How this entity was disambiguated
This entity first appeared as the object of triple T116816 — resolving that mention is where its identity was fixed. The disambiguator weighed these candidate entities and picked the highlighted one (or “None”, minting a new entity). This is how homonymy is resolved: the same surface form can point to different entities.
NED1
Entity disambiguation (via context triple)
gpt-5-mini-2025-08-07
Target entity: Rules for Inservice Inspection of Nuclear Power Plant Components Context triple: [ASME Boiler and Pressure Vessel Code, sectionXIName, Rules for Inservice Inspection of Nuclear Power Plant Components]
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A.
Rules for Construction of Nuclear Facility Components
Rules for Construction of Nuclear Facility Components is a section of the ASME Boiler and Pressure Vessel Code that sets design, fabrication, and quality assurance standards for components used in nuclear power and related facilities.
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B.
ASME Journal of Nuclear Engineering and Radiation Science
ASME Journal of Nuclear Engineering and Radiation Science is a peer-reviewed scholarly journal that publishes research on nuclear engineering, reactor technology, and radiation science.
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C.
ASME Boiler and Pressure Vessel Code
The ASME Boiler and Pressure Vessel Code is a globally recognized set of safety and design standards governing the construction, inspection, and maintenance of boilers and pressure vessels.
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D.
ASME Journal of Pressure Vessel Technology
The ASME Journal of Pressure Vessel Technology is a peer-reviewed scientific journal that publishes research and developments related to the design, analysis, materials, and integrity of pressure vessels and related components.
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E.
the ASME Pressure Vessels and Piping Conference
The ASME Pressure Vessels and Piping Conference is a major international technical conference focused on research, design, analysis, and operation of pressure vessels, piping systems, and related components in industries such as power, oil and gas, and nuclear.
- F. None of above. chosen
- G. Unsure - the case is ambiguous/there is not enough information to decide.
NED2
Entity disambiguation (via description)
gpt-5-mini-2025-08-07
Target entity: Rules for Inservice Inspection of Nuclear Power Plant Components Target entity description: Rules for Inservice Inspection of Nuclear Power Plant Components is a key section of the ASME Boiler and Pressure Vessel Code that establishes requirements for the periodic examination, testing, and maintenance of nuclear power plant components to ensure their continued safety and integrity.
-
A.
Rules for Construction of Nuclear Facility Components
Rules for Construction of Nuclear Facility Components is a section of the ASME Boiler and Pressure Vessel Code that sets design, fabrication, and quality assurance standards for components used in nuclear power and related facilities.
-
B.
ASME Journal of Nuclear Engineering and Radiation Science
ASME Journal of Nuclear Engineering and Radiation Science is a peer-reviewed scholarly journal that publishes research on nuclear engineering, reactor technology, and radiation science.
-
C.
ASME Boiler and Pressure Vessel Code
The ASME Boiler and Pressure Vessel Code is a globally recognized set of safety and design standards governing the construction, inspection, and maintenance of boilers and pressure vessels.
-
D.
ASME Journal of Pressure Vessel Technology
The ASME Journal of Pressure Vessel Technology is a peer-reviewed scientific journal that publishes research and developments related to the design, analysis, materials, and integrity of pressure vessels and related components.
-
E.
the ASME Pressure Vessels and Piping Conference
The ASME Pressure Vessels and Piping Conference is a major international technical conference focused on research, design, analysis, and operation of pressure vessels, piping systems, and related components in industries such as power, oil and gas, and nuclear.
- F. None of above. chosen
Statements (48)
| Predicate | Object |
|---|---|
| instanceOf |
ASME code section
ⓘ
technical standard ⓘ |
| addresses |
acceptability of indications
ⓘ
flaw evaluation ⓘ pressure boundary integrity ⓘ risk-informed inservice inspection (RI-ISI) approaches ⓘ |
| alsoKnownAs | ASME Section XI ⓘ |
| appliesTo |
Class 1 nuclear components
ⓘ
Class 2 nuclear components ⓘ Class 3 nuclear components ⓘ containment components ⓘ nuclear power plant components ⓘ pressure-retaining components in nuclear power plants ⓘ |
| contributesTo |
defense-in-depth in nuclear power plants
ⓘ
prevention of loss-of-coolant accidents ⓘ regulatory compliance for nuclear facilities ⓘ |
| defines |
acceptance standards for flaws
ⓘ
examination methods ⓘ inspection intervals ⓘ repair requirements ⓘ replacement requirements ⓘ |
| developedBy | American Society of Mechanical Engineers ⓘ |
| focusesOn |
inservice inspection
ⓘ
operating nuclear power plants ⓘ |
| geographicScope | internationally used standard ⓘ |
| hasAbbreviation | ASME Section XI ⓘ |
| hasPurpose |
ensure continued safety of nuclear power plant components
ⓘ
ensure continued structural integrity of nuclear power plant components ⓘ |
| includes |
pressure testing requirements
ⓘ
requirements for liquid penetrant testing ⓘ requirements for magnetic particle testing ⓘ requirements for radiographic testing ⓘ requirements for ultrasonic testing ⓘ requirements for visual examination ⓘ |
| partOf | ASME Boiler and Pressure Vessel Code ⓘ |
| regulates |
maintenance of nuclear power plant components
ⓘ
periodic examination of nuclear power plant components ⓘ periodic testing of nuclear power plant components ⓘ |
| relatedTo |
ASME Section III
ⓘ
linked to:
ASME Boiler and Pressure Vessel Code
nuclear safety regulation ⓘ |
| supports |
ageing management of nuclear power plants
ⓘ
defect detection in nuclear components ⓘ leakage control in nuclear power plants ⓘ |
| updatedBy | periodic ASME code editions and addenda ⓘ |
| usedBy |
inspection organizations
ⓘ
nuclear power plant operators ⓘ regulatory authorities ⓘ |
| uses | nondestructive examination methods ⓘ |
How these facts were elicited
The pipeline generated the facts above by prompting gpt-5.1 with this entity's name + description and the instruction below.
Instruction
You are a knowledge base construction expert. Given a subject entity and a description of it, return factual statements that you know for the subject as a JSON list of dictionaries(triples), where keys must be "subject", "predicate" and "object". The number of facts may be very high, between 25 to 50 or more, for very popular subjects. For less popular subjects, the number of facts can be very low, like 5 or 10. # Requirements - If you don't know the subject at all, return an empty list. - If the subject is not a named entity, return an empty list. - Include at least one triple where predicate is "instanceOf". - Do not get too wordy. - Separate several objects into multiple triples with one object.
Input
Subject: Rules for Inservice Inspection of Nuclear Power Plant Components Description of subject: Rules for Inservice Inspection of Nuclear Power Plant Components is a key section of the ASME Boiler and Pressure Vessel Code that establishes requirements for the periodic examination, testing, and maintenance of nuclear power plant components to ensure their continued safety and integrity.
Referenced by (4)
Full triples — surface form annotated when it differs from this entity's canonical label.
ASME Boiler and Pressure Vessel Code
→
sectionXIName
→
Rules for Inservice Inspection of Nuclear Power Plant Components
ⓘ
linked to: Rules for Inservice Inspection of Nuclear Power Plant Components
Rules for Inservice Inspection of Nuclear Power Plant Components
→
hasAbbreviation
→
ASME Section XI
ⓘ
linked to: Rules for Inservice Inspection of Nuclear Power Plant Components
linked to: Rules for Inservice Inspection of Nuclear Power Plant Components