ML21145A246

Advanced Reactors GEIS Docs - Current and Future Packaging Designs for Shipping ATF and HALEU Fuel Materials

ML21145A246
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Issue date:	05/25/2021
From:	NRC
To:	NRC/NMSS/DREFS
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Download: ML21145A246 (12)

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From:

Giacinto, Joseph Sent:

Tuesday, May 25, 2021 2:04 PM To:

AdvancedReactors-GEISDocsPEm Resource

Subject:

Current and Future Packaging Designs for Shipping ATF and HALEU Fuel Materials Attachments:

Hennebach-Langston,Daher2020.pdf

Current and Future Packaging Designs for Shipping ATF and HALEU Fuel Materials Presented by: Maik Hennebach and Andy Langston DAHER Nuclear Technologies, Germany DAHER-TLI, USA

Package Designs for ATF and HALEU Versa-Pac Model VP-55 Versa-Pac Model VP-55XL DN30 DN30-10 and DN30-20

3 Versa-Pac Model VP-55

4 General Package Design Current Contents Recent Addition of Content Types

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• Reduced enrichment loading level (1.25 wt.% U-235)

• Air transport configuration Increased payload weight

• Drop testing results Current NRC application includes the addition of TRISO fuel with enrichments up to 20 wt.% U-235 Shipment of 1S and 2S cylinder in process from Vienna to DOE site Future amendment to include 10 wt.% U-235 hydrogen restricted (1 lb of plastic) to allow up to 685g U-235 Versa-Pac VP-55 Licensing Overview

Versa-Pac VP-55 Loading Table U-235 Loading Table for VP-55 U-235 Loading Table for VP-55 with 5 Pipe 1S/2S Cylinder Limit for the VP-55 (up to 20 wt.% U-235) 1S/2S Cylinder Limit for the VP-55 with 5 Pipe (up to 100 wt.% U-235)

Hydrogen Restricted U-235 Loading Limits

Packaging / Contents Double height VP-55 Utilizes same internal support structure, thermal insulation and closure system as the VP-55 Internal cavity to be filled with shoring that provides positioning and

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Lifting and tiedown devices will be included for handling the package Cavity sized to accommodate 8A and 12B cylinders Planned Safety Analyses Credit some VP-55 NCT testing (e.g. vibration, water spray, penetration)

Physical drop testing with supplemental LS-DYNA analyses (e.g. worst-case drop angles)

ANSYS Thermal Analysis SCALE Criticality Analysis VP-55XL Introduction

DN30 New 30B overpack design Currently certifications include:

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quantities, and an enrichment of not more than 5 wt.%

U-235 in uranium. USA-9362-AF and F/420/AF

• Type IF for UF6 containing commercial grade or reprocessed uranium complying with the requirements for LSA-II, and an enrichment of not more than 5 wt.%

U-235 in uranium. F/420/IF

• Type B(U)F for UF6 containing commercial grade uranium or reprocessed uranium with an enrichment of not more than 5 wt.% U-235 in uranium. F/420/B(U)F

• CSI = 0 DN30 PSP 30B cylinder

DN30-X DAHER Nuclear Technologies is developing a new version of the DN30 to support ATF and HALEU production Packaging ŽŽŽh&

of up to 20 wt.% U-235 The DN30-X consists of the unmodified DN30 PSP and the new 30B-X cylinder The 30B-X cylinder adds a criticality control system to the standard ISO 7195/ANSI N14.1 30B cylinder.

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at 10 wt.% U-235 A design dedicated to a higher limit of 20 wt.% U-235 has a payload of up to 1250 kg UF6 DN30 PSP 30B-X cylinder

The Criticality Control System (CCS)

The CCS consists of steel rods (CCRs) filled with neutron absorbing material Positioning of the CCRs is ensured by lattice holders Whole CCS made of the same steel as the cylinder, ensuring material compatibility with both the UF6 and the cylinder walls Lower enrichment limits require fewer CCRs

Complete 30B-X cylinder Cylinder has same outer dimensions, material and interfaces (valve/plug) as standard 30B cylinder It will fit within current fuel fabrication process with no modifications Even without further markings, can be easily distinguished from standard 30B cylinder due to CCR penetrations on both sides y

Feasibility study completed in April 2020 Safety analysis report for DN30-X completed by Q4/2020 Application to be made to the NRC (pre-application meeting scheduled for May 2020)

Goal to achieve NRC certification Q4/2021 Initial fabrication of 30B-X starting Q1/2022 DN30-X Schedule