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| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Brady B M, NRR-DMLR 415-2981
| contact person = Brady B, NRR-DMLR 415-2981
| package number = ML18137A131
| package number = ML18137A131
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs
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=Text=
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{{#Wiki_filter:NRC's Research Perspectives on Irradiated ConcreteMadhumita Sircar US Nuclear Regulatory Commission Office of Nuclear Regulatory ResearchNEI-EPRI Concrete Workshop Washington, DC May 17, 2018 Overview*Objectives and Outcome
{{#Wiki_filter:NRCs Research Perspectives on Irradiated Concrete Madhumita Sircar US Nuclear Regulatory Commission Office of Nuclear Regulatory Research NEI-EPRI Concrete Workshop Washington, DC May 17, 2018
*Engagement
 
*Plant Specific Information
Overview
*Additional Knowledge Development 2
* Objectives and Outcome
* Engagement
* Plant Specific Information
* Additional Knowledge Development 2
 
Research Perspectives
* Reactor pressure vessel (RPV) generally supported under the inlet and/or outlet nozzles
* Nearest load-bearing concrete depends on the nozzle support design
* RPV supported on concrete bioshield (CBS)
* RPV supported on steel columns and horizontal steel frame anchored to CBS for lateral load transfer
* Other safety related concrete structure and components close to RPV Reactor Concepts Manual (ML15252A444)
 
Research Perspectives Objectives
  - Estimation of expected level of radiation (neutron E>0.1 MeV and gamma) on concrete for the period of SLR (up to 80 years of operation) and propagation of radiation through concrete section
  - Characterization of degradation due to radiation
  - Characterization of concrete damage depth under structural constraints
  - Structural significance for long-term operations considering current licensing basis design
  - Programmatic aspects for managing the aging effects 4
 
Research Perspectives Outcome
  - Approaches for confirmatory review of industry research to assess structural performance for the structures exposed to high radiation
  - Technical bases to support updating regulatory guidance for structures exposed to high irradiation for operating life up to 80 years (SLR).
5
 
Research Perspectives
Research Perspectives
*Reactor  pressure vessel  (RPV) generally supported under the inlet and/or outlet nozzles
* Engagements
*Nearest load
  - NRC is conducting confirmatory research
-bearing concrete depends on the nozzle support design
  - NRC-DOE-EPRI joint research MOU and roadmap
*RPV supported on concrete bioshield(CBS) *RPV supported on steel columns and horizontal steel frame anchored to CBS for lateral load transfer
  - NRC-NRA (Japan) bi-lateral research MOU - NRC received experimental data from recently completed NRAJ research
*Other safety related concrete structure and components close to  RPVReactor Concepts Manual (ML15252A444)
  - Participating in International Committee on Irradiated Concrete (ICIC) 6
Research PerspectivesObjectives
 
-Estimation of expected level of radiation (neutron E>0.1 MeVand gamma) on concrete for the period of SLR (up to 80 years of operation) and propagation of radiation through concrete section
Estimated 80-Year Neutron Fluence (E > 0.1 MeV) on Concrete Estimated 80 Year Neutron Fluence (E >0.1 MeV) at Outer RPV (Inner face of concrete is about 10% less).
-Characterization of degradation due to radiation-Characterization of concrete damage depth under structural constraints
Source: ORNL/TM-2018/769 7
-Structural significance for long
 
-term operations considering current licensing basis design
Plant-Specific Information to Develop Basic Understanding
-Programmatic aspects for managing the aging effects 4
  - Current neutron fluence and gamma dose information
Research PerspectivesOutcome-Approaches for confirmatory review of industry research to assess structural performance for the structures exposed to high radiation
  - Plant configuration and structural details of RPV supports and bioshield wall
-Technical bases to support updating regulatory guidance for structures exposed to high irradiation for operating life up to 80 years (SLR).
  - Concrete composition (aggregates, cement, grout, etc.),
5 Research Perspectives
reinforcement and supports anchorage
*Engagements
  - Environment (temperature and humidity)
-NRC is conducting confirmatory research
  - CBS liner and attachment
-NRC-DOE-EPRI joint research MOU and roadmap
  - Current Licensing Basis design requirements (method, load combination, design codes)
-NRC-NRA (Japan) bi-lateral research MOU  
  - Inspection and monitoring methods 8
-NRC received experimental data from recently completed NRAJ research
 
-Participating in International Committee on Irradiated Concrete (ICIC) 6 Estimated 80
-Year Neutron Fluence (E > 0.1 MeV) on Concrete 7Estimated 80 Year Neutron Fluence (E >0.1 MeV) at Outer RPV (Inner face of concrete is about 10% less). Source: ORNL/TM
-2018/769 Plant-Specific Information to Develop Basic Understanding
-Current neutron fluence and gamma dose information
-Plant configuration and structural details of RPV supports and bioshield wall
-Concrete composition (aggregates, cement, grout, etc.), reinforcement and support sanchorage-Environment (temperature and humidity
)-CBS liner and attachment
-Current Licensing Basis design requirements (method, load combination, design codes
)-Inspection and monitoring methods 8
Plant-Specific Information to Develop Basic Understanding
Plant-Specific Information to Develop Basic Understanding
*Support details
* Support details
*Local design considerations  
* Local design considerations - concrete, rebar, anchorages
-concrete, rebar, anchorages  
* Characterization of load-resisting mechanisms (for example, steel-concrete bond strength)
*Characterization of load
Source: WCAP-14422 Rev. 2-A
-resisting mechanisms (for example, steel
 
-concrete bond strength)Source: WCAP
Additional Knowledge Development Irradiated Steel-Concrete Bond Strength [Significant]
-14422 Rev. 2-A Irradiated Steel
    - Possible loss of bond due to the irradiation-induced damage of concrete around rebars and support anchorages Rate Effects
-Concrete Bond Strength [Significant]
    - Require concrete harvested from decommissioned LWR NPPs
-Possible loss of bond due to the irradiation
* at high dose, i.e., > 1019 n.cm-2 @ E > 0.1 MeV
-induced damage of concrete around rebars and support anchoragesRate Effects
* w/ high silica content aggregate No relevant harvesting opportunity as of today.
-Require concrete harvested from decommissioned LWR NPPs  
Likely source San Onofre, Keewaunee Examination of In-Situ Damage, Monitoring, and Aging Management approaches Irradiated Concrete Creep
*at high dose, i.e., > 10 19n.cm-2@ E > 0.1 MeV
    - Need for experimental data. Concrete creep may affect irradiation-induced cracking Irradiation-Assisted Alkali-Silica Reaction
*w/ high silica content aggregate No relevant harvesting opportunity as of today.Likely source San Onofre , KeewauneeExamination of In
    - Irradiation-induced amorphization increases the dissolution rate of aggregates 1
-Situ Damage, Monitoring, and Aging Management approachesIrradiated Concrete Creep
 
-Need for experimental data. Concrete creep may affect irradiation
QUESTIONS?}}
-induced crackingIrradiation
-Assisted Alkali
-Silica Reaction  
-Irradiation
-induced amorphization increases the dissolution rate of aggregates g Additional Knowledge Development 1 0 QUESTIONS?}}

Latest revision as of 03:54, 21 October 2019

NEI-NRC Workshop Irradiated Concrete - RES, May 17, 2018
ML18137A134
Person / Time
Issue date: 05/17/2018
From: Madhumita Sircar
NRC/RES/DE/SGSEB
To:
Brady B, NRR-DMLR 415-2981
Shared Package
ML18137A131 List:
References
Download: ML18137A134 (11)
v • d • e


Text

NRCs Research Perspectives on Irradiated Concrete Madhumita Sircar US Nuclear Regulatory Commission Office of Nuclear Regulatory Research NEI-EPRI Concrete Workshop Washington, DC May 17, 2018

Overview

  • Objectives and Outcome
  • Engagement
  • Plant Specific Information
  • Additional Knowledge Development 2

Research Perspectives

  • Nearest load-bearing concrete depends on the nozzle support design
  • RPV supported on concrete bioshield (CBS)
  • RPV supported on steel columns and horizontal steel frame anchored to CBS for lateral load transfer
  • Other safety related concrete structure and components close to RPV Reactor Concepts Manual (ML15252A444)

Research Perspectives Objectives

- Estimation of expected level of radiation (neutron E>0.1 MeV and gamma) on concrete for the period of SLR (up to 80 years of operation) and propagation of radiation through concrete section

- Characterization of degradation due to radiation

- Characterization of concrete damage depth under structural constraints

- Structural significance for long-term operations considering current licensing basis design

- Programmatic aspects for managing the aging effects 4

Research Perspectives Outcome

- Approaches for confirmatory review of industry research to assess structural performance for the structures exposed to high radiation

- Technical bases to support updating regulatory guidance for structures exposed to high irradiation for operating life up to 80 years (SLR).

5

Research Perspectives

  • Engagements

- NRC is conducting confirmatory research

- NRC-DOE-EPRI joint research MOU and roadmap

- NRC-NRA (Japan) bi-lateral research MOU - NRC received experimental data from recently completed NRAJ research

- Participating in International Committee on Irradiated Concrete (ICIC) 6

Estimated 80-Year Neutron Fluence (E > 0.1 MeV) on Concrete Estimated 80 Year Neutron Fluence (E >0.1 MeV) at Outer RPV (Inner face of concrete is about 10% less).

Source: ORNL/TM-2018/769 7

Plant-Specific Information to Develop Basic Understanding

- Current neutron fluence and gamma dose information

- Plant configuration and structural details of RPV supports and bioshield wall

- Concrete composition (aggregates, cement, grout, etc.),

reinforcement and supports anchorage

- Environment (temperature and humidity)

- CBS liner and attachment

- Current Licensing Basis design requirements (method, load combination, design codes)

- Inspection and monitoring methods 8

Plant-Specific Information to Develop Basic Understanding

  • Support details
  • Local design considerations - concrete, rebar, anchorages
  • Characterization of load-resisting mechanisms (for example, steel-concrete bond strength)

Source: WCAP-14422 Rev. 2-A

Additional Knowledge Development Irradiated Steel-Concrete Bond Strength [Significant]

- Possible loss of bond due to the irradiation-induced damage of concrete around rebars and support anchorages Rate Effects

- Require concrete harvested from decommissioned LWR NPPs

  • at high dose, i.e., > 1019 n.cm-2 @ E > 0.1 MeV
  • w/ high silica content aggregate No relevant harvesting opportunity as of today.

Likely source San Onofre, Keewaunee Examination of In-Situ Damage, Monitoring, and Aging Management approaches Irradiated Concrete Creep

- Need for experimental data. Concrete creep may affect irradiation-induced cracking Irradiation-Assisted Alkali-Silica Reaction

- Irradiation-induced amorphization increases the dissolution rate of aggregates 1

QUESTIONS?

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