Triple

T23071786
Position Surface form Disambiguated ID Type / Status
Subject ASME Codes and Standards E575215 entity
Predicate includesStandard P19701 FINISHED
Object ASME OM Operation and Maintenance of Nuclear Power Plants NE NERFINISHED

How this triple was built (3 steps)

Every LLM step that produced this triple, in pipeline order — named-entity classification, the disambiguation choices (the exact options shown, with the pick highlighted), and the generated description. The batch + timestamp of each is in the Provenance table below.

NER Named-entity recognition gpt-5-mini
Instruction
Given a phrase, classify it is english named entity (e.g., persons, organizations, works of art) in Latin script, or not (e.g., literals, dates, URLs, verbose phrases). For disambiguation, the statement where the phrase occurs as object is also given. Please return a JSON object with `phrase` (string, the phrase being analyzed) and `is_ne` (boolean, indicating whether the phrase is a Named Entity).
Input
Phrase: ASME OM Operation and Maintenance of Nuclear Power Plants | Statement: [ASME Codes and Standards, includesStandard, ASME OM Operation and Maintenance of Nuclear Power Plants]
NED1 Entity disambiguation (via context triple) gpt-5-mini-2025-08-07
Target entity: ASME OM Operation and Maintenance of Nuclear Power Plants
Context triple: [ASME Codes and Standards, includesStandard, ASME OM Operation and Maintenance of Nuclear Power Plants]
  • A. Rules for Inservice Inspection of Nuclear Power Plant Components
    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.
  • B. 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.
  • C. 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.
  • D. NRC Reactor Oversight Process
    The NRC Reactor Oversight Process is the U.S. Nuclear Regulatory Commission’s standardized framework for monitoring, assessing, and enforcing the safety and security performance of commercial nuclear power reactors.
  • E. IAEA Nuclear Energy Series
    The IAEA Nuclear Energy Series is a collection of technical publications by the International Atomic Energy Agency that provide guidance, standards, and best practices for the safe, secure, and sustainable use of nuclear energy.
  • 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: ASME OM Operation and Maintenance of Nuclear Power Plants
Target entity description: ASME OM Operation and Maintenance of Nuclear Power Plants is a key American Society of Mechanical Engineers standard that provides technical requirements and guidance for the safe, reliable operation, testing, and maintenance of systems and components in nuclear power plants.
  • A. Rules for Inservice Inspection of Nuclear Power Plant Components
    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.
  • B. 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.
  • C. 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.
  • D. NRC Reactor Oversight Process
    The NRC Reactor Oversight Process is the U.S. Nuclear Regulatory Commission’s standardized framework for monitoring, assessing, and enforcing the safety and security performance of commercial nuclear power reactors.
  • E. IAEA Nuclear Energy Series
    The IAEA Nuclear Energy Series is a collection of technical publications by the International Atomic Energy Agency that provide guidance, standards, and best practices for the safe, secure, and sustainable use of nuclear energy.
  • F. None of above. chosen

Provenance (2 batches)

The batch behind each pipeline step, in order, with when it ran. Timestamps are batch-level — stages were processed in waves, so the object chain (NER → NED1 → NEDg → NED2) reads in order, but predicate / elicitation batches can sit in a different wave.

Step Stage Batch ID Status When
creating Elicitation batch_69e245bd6e4c8190bb8942245b68cad5 completed April 17, 2026, 2:37 p.m.
NER Named-entity recognition batch_69f18c5ffad881909ed626045c15dd33 completed April 29, 2026, 4:43 a.m.
Created at: April 17, 2026, 3:56 p.m.