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A list of all pages that have property "Title" with value "Presentations for 15th International Conference on Fracture". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20267A090  + (Presentation to the National Academies of Science, Math, and Medicine Committee on the Overview of the NRCs Regulatory Programs on the Advanced Reactor Fuel Cycle)
  • PMNS20240877, Presentation to the Pope County Quorum Court of the Nuclear Regulatory Commissions 2023 Annual Assessment of Safety Performance at Arkansas Nuclear One  + (Presentation to the Pope County Quorum Court of the Nuclear Regulatory Commissions 2023 Annual Assessment of Safety Performance at Arkansas Nuclear One)
  • PMNS20230582, Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commissions 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station  + (Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commissions 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station)
  • ML19340A391  + (Presentation, Approach for Responding to Draft Requests for Additional Information Related to NRC Review of Topical Report EPRI-AR-1(NP))
  • ML061000273  + (Presentation, Braidwood Generating Station Groundwater Update)
  • ML23067A315  + (Presentation, Case N-847-1, Excavate and Weld Repair, Technical Exchange with Electric Power Research Institute Welding and Repair Technology)
  • ML061070598  + (Presentation, Groundwater Update Meeting)
  • ML22014A019  + (Presentation, Materials for January 20, 2022, ACRS Subcommittee Meeting (Accident Analysis- T-H Subcommittee))
  • ML23067A340  + (Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology)
  • ML19340A291  + (Presentation, TRISO Fuel Performance Topical Report)
  • ML042610044  + (Presentation- NEI 99-01 Upgrade EALs)
  • ML13155A447  + (Presentation-NRC/Research Use of Deterministic Tools for SFP Analysis in the Vogtle Units 1 & 2 Site)
  • ML25220A273  + (Presentation: Centrifuge Storage Building - CASS Exemption Request Pre Application Meeting (August 14, 2025))
  • ML18199A297  + (Presentation: Defining Unacceptable Radiological Consequences from a Security Perspective)
  • ML19214A056  + (Presentation: Duke Energy Presubmittal Meeting - August 7, 2019)
  • ML19233A046  + (Presentation: Harris/Nrc Pre-submittal Meeting: Risk-Informed Completion Times, August 22, 2019)
  • ML090790850  + (Presentation: Introduction to Nuclear Graphite Workshop)
  • ML18284A453  + (Presentation: Meeting Handout for Pre-Application Meeting for Certificate of Compliance No. 1014 for HI-STORM 100, Amendment No. 14)
  • ML18029A821  + (Presentation: NRC 10 CFR 61 Update on Low-Level Waste Management)
  • ML20339A385  + (Presentation: NRC Technical Assessment of Additive Manufacturing - Laser Powder Bed Fusion)
  • ML20283A616  + (Presentation: NRCs Preparations for Advanced Reactor Licensing, ORNL Molten Salt Workshop, October 14-15, 2020)
  • ML24338A167  + (Presentation: Overview of NRC Licensing for U.S. Navy)
  • ML22130A523  + (Presentations - May 11, 2022 Advanced Reactor Stakeholder Meeting)
  • ML24074A353  + (Presentations - RIC2024 - TH19 - Long-Term Operations: Meeting the Moment)
  • ML17171A198  + (Presentations by Members of the Public - Indian Point Annual Assessment Meeting)
  • ML23193B039  + (Presentations for 15th International Conference on Fracture)
  • ML18012A096  + (Presentations for Industry NRC Nondestructive Examination Technical Information Exchange Public Meetings on January 16 - 18, 2018)
  • ML20211L080  + (Presentations for July 30, 2020 Higher Burnup Workshop - NEI Presentation)
  • ML20211L089  + (Presentations for July 30, 2020 Higher Burnup Workshop - Nuclear Energy Agency Presentation)
  • ML20211L086  + (Presentations for July 30, 2020 Higher Burnup Workshop - NRC Quality Submittals)
  • ML20211L077  + (Presentations for July 30, 2020 Higher Burnup Workshop - EPRI Presentation)
  • ML20211L091  + (Presentations for July 30, 2020 Higher Burnup Workshop - Westinghouse Presentation)
  • ML20211L082  + (Presentations for July 30, 2020 Higher Burnup Workshop - NRC Overview)
  • ML22319A120  + (Presentations for Lessons Learned Public Meeting 11-15-2022)
  • ML19291D231  + (Presentations for October 17, 2019 Regulatory Issues Task Force (RITF) Meeting (Part 2))
  • ML19289D095  + (Presentations for October 17, 2019, Regulatory Issues Task Force (RITF) Public Meeting)
  • ML22137A276  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
  • ML22137A292  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
  • ML22137A279  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
  • ML22137A286  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
  • ML22137A176  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
  • ML22137A144  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
  • ML22137A167  + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
  • ML21230A354  + (Presentations for the Extremely Low Probability of Rupture (Xlpr) Probabilistic Fracture Mechanics Code User Experience Webinar, August 18, 2021)
  • ML17296A216  + (Presentations on Reactor Decommissioning at Ma Ndcap at Plymouth Ma Public Meeting Oct 18, 2017)
  • ML19095A728  + (Presenting Results of Outstanding Questions in IE Bulletins Nos. 75-04 and 75-04A)
  • ML18347A545  + (Presenting Short-Term Measures Implemented to Minimize Potential Reactor Vessel Overpressurizations, as Responded in Letter of 10/7/1976)
  • ML19095A284  + (Presenting, Unit 2 Steam Generator Surveillance Program Outage Schedule & Information of Program)
  • ML16341B122  + (Presents ACRS Conclusion from 781102-04 Meeting That Dr Lucos Concerns Re Seismic Eval Bases for Subj Facils Were Considered in Findings & Recommendations in 780714 ACRS Rept)
  • ML20138F090  + (Presents ACRS Position on Indian Point Special Proceeding. Schedule & Plan Development Recommended to Reduce Estimated Core Melt Frequency & Uncertainty.Detailed Containment Performance Evaluation for Particular Sites Suggested)
  • ML20216J851  + (Presents Actions Staff Will Undertake to Develop Rulemaking for Transitioning to More risk-informed,performance-based Structure for Fire Protection Regulation at Nuclear Power Plants)