ML22088A189

From kanterella
Revision as of 12:35, 18 November 2024 by StriderTol (talk | contribs) (StriderTol Bot change)
Jump to navigation Jump to search
Impacts of Hbu, IE and ATF on Radiological Source Terms, 3rd Joint EPRI-INL Higher Burnup Workshop March 2022
ML22088A189
Person / Time
Issue date: 03/31/2022
From: Paul Clifford
NRC/NRR/DSS
To:
Paul Clifford NRR/DSS 301-415-4043
References
Download: ML22088A189 (13)
v • d • e


Text

Impacts of HBU, IE and ATF on Radiological Source Terms

3rd Joint EPRI-INL Higher Burnup Workshop March 2022

Paul Clifford Senior Technical Advisor for Reactor Fuel NRC/NRR/DSS Types of Radiological Source Terms

  • Radiological source terms for postulated accidents:
1) MHA-LOCA, which is based on a generic, deterministic, core-average, fuel melt source term
2) Non-LOCA DBA, which are based on site-specific, mechanistic, peak fuel rod, source terms

2 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBUIncreased Doped UO2Coated F e C r Al BU 68-75235U Fuel Zirconium Cladding 62-68Enrichment Cladding

Core Average Radionuclide Inventories

Core Average Decay Heat

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum)

Fuel Rod Damage (Number of Failed Fuel Rods)

Transient Radionuclide Release Fractions

Fuel Rod Power Peaking Factors ( FdH)

3 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories

Core Average Decay Heat

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum)

Fuel Rod Damage (Number of Failed Fuel Rods) - -

Transient Radionuclide Release Fractions

Fuel Rod Power Peaking Factors ( FdH) - -

4 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories

Core Average Decay Heat

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum)

Fuel Rod Damage (Number of Failed Fuel Rods) - -

Transient Radionuclide Release Fractions

Fuel Rod Power Peaking Factors ( FdH) - -

5 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories - -

Core Average Decay Heat - -

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form - -

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum) Proprietary

Fuel Rod Damage (Number of Failed Fuel Rods) - - Proprietary

Transient Radionuclide Release Fractions Proprietary

Fuel Rod Power Peaking Factors ( FdH) - - - -

6 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories - - - -

Core Average Decay Heat - - - -

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form - - - -

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum) Proprietary - -

Fuel Rod Damage (Number of Failed Fuel Rods) - - Proprietary ?

Transient Radionuclide Release Fractions Proprietary - -

Fuel Rod Power Peaking Factors ( FdH) - - - - - -

7 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories - - - - ?

Core Average Decay Heat - - - - ?

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form - - - - ?

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum) Proprietary - - ?

Fuel Rod Damage (Number of Failed Fuel Rods) - - Proprietary ? ?

Transient Radionuclide Release Fractions Proprietary - - ?

Fuel Rod Power Peaking Factors ( FdH) - - - - - - ?

8 Impacts on Radiological Inputs and Assumptions

Radiological Inputs / Assumptions Extended HBU Increased Doped UO2 Coated F e C r Al BU 68-75 235U Fuel Zirconium Cladding 62-68 Enrichment Cladding

Core Average Radionuclide Inventories - - - - ?

Core Average Decay Heat - - - - ?

Core Average MHA-LOCA Release Fractions, Timing, Chemical Form - - - - ?

Steady-State Radionuclide Release Fractions (Pellet Rod Plenum) Proprietary - - ?

Fuel Rod Damage (Number of Failed Fuel Rods) - - Proprietary ? ?

Transient Radionuclide Release Fractions Proprietary - - ?

Fuel Rod Power Peaking Factors ( FdH) - - - - - - ?

9 License Amendment Requests

  • Licensees should evaluate their plants license bases associated with radiological consequence assessments to determine potential impacts of HBU, IE, and ATF

- Existing source terms likely limited to 62 GWd/MTU rod average and existing fuel designs

  • Licensees will likely need to submit a LAR to address impacts on radiological consequence assessments

- Changes to radiological source terms not allowed under 10 CFR 50.59 provisions*

  • 10 CFR 50.67 Statement of Considerations states that changes to the fraction of the fission product inventory of the radionucl ides released from the reactor fuel, their chemical and physical form, or the timing of their releases should not be implemented under 10 CFR 50.59..

10 Regulatory Guidance

  • DG-1389 provides updated guidance for calculating AST radiological consequences

- Future revision to RG 1.183

  • Applicability expanded to support near-term industry objectives

- MHA-LOCA source term applicable up to 68 GWd /MTU rod average burnup, 8.0 wt % 235U, Chromia-doped UO2 fuel, and coated zirconium cladding

- Deterministic, core-average melt source term less sensitive to rod design and power history

- Revised source terms to support HBU (beyond 68) under development

11 Regulatory Guidance

- Non-LOCA DBA source term applicable up to 68 GWd /MTU rod average burnup for expanded operating domain

- Mechanistic, peak rod source term sensitive to rod design and power history

- Too many degrees of freedom in design and operations

- Vendor proprietary fuel properties

- Acceptable analytical method for calculating plant-specific release fractions provided in updated guidance

12 QUESTIONS?

13

Retrieved from "https://kanterella.com/w/index.php?title=ML22088A189&oldid=3731242"