ML25114A172
| ML25114A172 | |
| Person / Time | |
|---|---|
| Site: | 07109309 |
| Issue date: | 04/24/2025 |
| From: | Global Nuclear Fuel |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML25114A170 | List: |
| References | |
| M250154 | |
| Download: ML25114A172 (1) | |
Text
ENCLOSURE 1 M250154 Open Session Presentation Slides for RAJ-II Meeting Non-Proprietary Information
Non-Proprietary Information GNr Gllobal Nuclear IFuel GNF 11x11 LUA IN RAJ-II LETTER AUTHORIZATION PRE-SUBMITTAL
Non-Proprietary Information Agenda and Speakers - Open Session Meeting to discuss the need for a Letter Authorization to allow shipment of a new fuel design as Lead Use Assemblies Open Session:
Overview of the LUA Design - Weston Cundiff Overview of the RAJ-II Package Safety Basis - Nate Wolk GNr Gllobal Nuclear IFuel 2
GNr Global Nuclear Fuel OPEN SESSION
Non-Proprietary Information GNr LUA Purpose & Design Overview Gllobal Nuclear IFuel Lead Use Assembly (LUA) Definition: Pre-production prototype of a new fuel design, which contains a new design features that are distinctly different from previous fuel designs.
Purpose of LUAs: Confirm expected operation of a new fuel design rather than to gather specific technical information.
New Fuel Design:
11 x11 fuel matrix Utilizes currently used and/or approved materials Mechanical design similar to current GNF fuel products 4
Non-Proprietary Information Chapter 1 - General Information Certificate of Compliance (CoC) USA/9309/B(U)F-96, Revision 14 NRC approved for Type B fissile material up through 8 wt% 235U Composed of an Outer Container (OC) and Inner Container (IC)
Stainless Steel (SS) OC body and lid, with impact absorbers SS IC body and lids, with alumina silicate thermal insulator Inner Container contains cavities to hold up to two fuel assemblies, or loose rods Fuel rod cladding and welded end plugs act as primary containment GNr Gllobal Nuclear IFuel 5
Non-Proprietary Information GNr Chapter 2 - Structural Gllobal Nuclear IFuel Full scale Certification Test Units (CTUs) passed free drop and puncture tests demonstrating containment of the fuel, geometric configuration stability for criticality safety, and protection for the fuel.
Deformation of the containers is limited by its redundant structure Limited OC deformation due to shock absorbers. Deformation of the IC is limited and only in length CTUs confirm the conservative nature of the geometry assumptions used in the criticality assessment LS-DYNA Finite Element Analysis (FEA) drop models of RAJ-II with GNF 10x10 and 11x11 fuel ballast developed using CTU test data to benchmark 6
Non-Proprietary Information Chapter 3 - Thermal GNr Gllobal Nuclear IFuel BWR fuel rods are pressurized to a maximum pressure of 1.1145 MPa (absolute, 162 psia) with helium at ambient temperature prior to sealing Normal Conditions of Transport (NCT)
Thermal loads solely from solar radiant heat Ambient temperatures from -40°C to 38°C (-40°F to 100°F) are considered Max temperature 77°C (171°F); max pressure 1.33 MPa (193 psia)
Hypothetical Accident Conditions (HAC) 800°C (1475°F) fire for half-hour with insolation before and after fire event Max temperature at RAJ-II inner container: 648°C (1198°F)
Max temperature of 648°C (1198°F) under all transportation conditions; max BWR internal rod pressure of 3.50 MPa (508 psia) 7
Non-Proprietary Information GNr Chapters 4/5 - Containment & Shielding Gllobal Nuclear IFuel The fuel rod cladding and ceramic nature of the fuel pellets provide primary containment of the radioactive material. The containment system includes the ceramic sintered pellet, clad in zirconium tubes which are welded and leak tested prior to shipment.
The contents of the RAJ-II require no shielding since unirradiated fuel gives off no significant radiation either gamma or neutron.
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Non-Proprietary Information Chapter 6 - Criticality Safety Analysis GNr Water exclusion is not required for this package. The package is analyzed in both undamaged and damaged arrays under optimal moderation and demonstrated to be safe under NCT and HAC Sensitivity analyses are performed by varying fuel parameters (rod pitch, clad OD, pellet OD, fuel orientation, polyethylene quantity, moderator density) to determine the most reactive configuration No credit for: Gadolinia rods, structural components outside the active fuel length, or spacers.
Honeycomb replaced by water, conservatively model the polyethylene to be around fuel rod cladding KENO-VI with the ENDF/B-VII continuous-energy neutron cross-section library Gllobal Nuclear IFuel 9