interaction of package design …. bernhard droste patram 2010 plenary october 5, ... the problem of...

Dr. Bernhard Droste PATRAM 2010 Plenary October 5, 2010 1

- DEVELOPMENT AND ASSESSMENT OF PACKAGES FOR TRANSPORT AND STORAGE OF RADIOACTIVE MATERIALS WITHIN DECOMMISSIONING ACTIVITIES -

Bernhard DrosteBAM Federal Institute for Materials Research and Testing

IMO, London, UK Plenary October 5, 2010

INTERACTION OF PACKAGE DESIGN DEVELOPMENTAND PACKAGE DESIGN SAFETY ASSESSMENT


Presentation Outline

This presentation will be a walk across many of thePATRAM conference topics:

1. Package Design Development Principles

2. Transport and Interim Storage of vitrified high-level Waste (HLW)

3. Mechanical Testing of a new HLW Dual Purpose Cask Design

4. Mechanical and thermal Design Aspects

5. Interim Storage of spent nuclear Fuel in Transport Casks

6. Drop Testing of LLW/MLW Disposal Containers

7. Transport and Storage of Large Components from NPP Dismantling

8. Conclusions


BAM

Package Design Development / Safety Assessment Fields

Assessment Report

Package Design Approval Certificate

BfSMechanical Design

Thermal Design

ManagementSystem

ExternalDose Rate

Criticality Safety(Fissile)

Package Conformity Certificate

Structure of Competent Authority Activities in Transport Package

Approval in Germany

Containment Design RadionuclideInventory


The Goal:

• reference to satisfactory previous tests of similar nature

• calculations or reasoned arguments with generally agreed methods and parameters, reasonably conservative

• experimental testing of small-scale or full-scale packaging model/dummy inventory

• a combination of all methods ( what is usually always the case…)

Design & Safety assessment of package performance under all relevant regulatory requirements, using

Package Design Development Principles

…under consideration of all variations of regulatory or operational conditions, geometry or properties tolerances and of test model/computational model/

serial package/inventory variations within the approved specifications


Complexity of Package Design Development


Structure and contents of the PDSR

Part 1

Contents list

Package Design Safety Report

Part 2Structural Analysis

Subdocument (if necessary)

Subdocument (if necessary)

Thermal Analysis

Containment Design Analysis

External Dose Rates Analysis

Criticality Safety Analysis

Administrative Information

Specification of Radioactive Contents

Specification of Packaging

Design Drawing, Drawing List, Material Specification, Manufacturing ...

Containment Specification Confinement Specification

Package Performance Characteristics

Compliance with Regulatory Requirements

Operation

Management System

Package Illustration

Maintenance

Source: F. Nitsche et al. PATRAM 2007

THE EUROPEAN TECHNICAL GUIDE ON PACKAGE DESIGN SAFETY REPORTS FOR TRANSPORT PACKAGES CONTAINING RADIOACTIVE MATERIAL


Basket

Impact Limiter

Shielding Thermal

Criticality

Cask Mass

Keff

Dose RateDesign Criteria

Moderator Expansion

ComponentTemperatures

Inventory Data Handling

Wall StructureDeceleration

Cavity Pressure

Lid SystemCask Body

Ref

eren

ce: G

NS

mbH

Fuel Rod Temperature

Containment

Release

Mechanics

Basket

Impact Limiter

ShieldingShielding ThermalThermal

CriticalityCriticality

Cask MassCask Mass

KeffKeff

Dose RateDesign Criteria

Moderator Expansion

ComponentTemperatures

Inventory Data Handling

Wall StructureDeceleration

Cavity Pressure

Lid SystemCask Body

Ref

eren

ce: G

NS

mbH

Fuel Rod Temperature

ContainmentContainment

ReleaseRelease

Mechanics

A Package Designer´s View


HLW Transport Campaigns from France to Germany

Transport of 11 TN85 Casks by Road from La Hague to Valognes, by Rail to Dannenberg and by Road to Interim Storage Facility Gorleben (2008)

Fotos: NCS


Rail/Road Transfer of a HLW Cask at Dannenberg

Cold Trial of a CASTOR HAW28M Cask (GNS)


Transport Casks Interim Storage Facility Gorleben for HLW (and SF)

Current Inventory (October 2010):-86 HLW Casks (1 TS 28V, 74 CASTOR HAW 20/28CG, 11 TN 85)

-5 SF Casks (1 CASTOR Ic, 1 CASTOR IIa, 3 CASTOR V/19)Foto: GNS


Transport Casks for Interim Storage of Vitrified High-Level Waste

TN 85 (TN-I) CASTOR HAW28M (GNS)

Drop Test 1:3 Model TN 81 Drop Test 1:2 Model CASTOR HAW TB/2


Experimental mechanical Testing

A.MusolffOral Presentation 172

SessionT 28Wednesday Oct. 6th

11:00-13:00


Mechanical Package Design Development/Assessment I

Numerical Stress Calculationof original Cask Design with verified FEM Model

Mechanical Assessment Strategyincludes experimental and

computational Methods

M. Weber Oral Presentation 026/115

Session T 19Tuesday Oct. 5th

16:00-18:00

F. WilleOral Presentation 124

Session T 16Monday Oct. 4th

U. ZenckerOral presentation 219

Session T 45Thursday Oct. 7th

11:00-12:40


Numerical Analysis of 9 m horizontal Drop onto radial Aluminium Impact Limiters

L. QiaoOral Presentation 117

Session T 16Monday Oct. 4th

Mechanical Package Design Development/Assessment II


Mechanical Package Design Development/Assessment III

Finite Element Analysis(here: 9 m horizontal Drop)

Completely Dynamic Quasi-Staticwith verified

dynamic factor

S. Komann et al.Presentation 042Poster Session

Wednesday Oct. 6th


Investigation of shock-absorbing MaterialsBAM Research Project ENREA investigates Wood, Polyurethane Foam and Damping

Concrete for Development of appropriate Material Models for Numerical Analysis

EFFECT OF DYNAMIC LOADING ON COMPRESSIONAL BEHAVIOR OF DAMPING CONCRETE

constant displacement-driven impact (3 m/s) on unconfined damping concrete specimen

Stress-strain curves for confined specimen

E. KasparekOral Presentation 114

Session T 40Thursday Oct. 7th

11:00-13:00


Cask in transport frame

Cask in Handling/Rotation Frame

Mechanical Package Design Aspects

Frames used for the Operation of CASTOR KNK Transport and Storage Cask (WTI/GNS)

The Problem of considering the Influence of a Transport FrameIf the transport frame is not detached from the packagebefore the maximum accident impact occurs, the framehas to be considered as integral part of the package

More clarification needed in the next IAEA TS-R-1/TS-G1.1 Revision

Cask in Transport Frame


Images: C. Bletzer, BAM-III.43

Thermal Package Design Development/ Assessment

Use of CFD calculations, and control of canopy compliancewith the design safety analysis report, handling instructions

The Problem of considering the Influence of a Canopy on Heat Removal


Fire Test Facilities at BAM Test Site Technical Safety

Fire Test Facility B

Fire Test Facility A

B. Droste et al.Presentation 218Poster Session

WednesdayOct. 6th


Spent Fuel Transport Cask NCS 45

Drop Test 1:3 Model


Spent Fuel Transport Casks Interim Storage on At-Reactor Sites

ZLN Lubmin, CASTOR WWER440 Casks

200th CASTOR V Cask (GNS) Delivery,Transfer to Interim Storage Facility

at NPP Lingen

at every NPP in Germany


Long-term Interim Storage of Spent Fuel in Transport Casks

The Problem of Ageing Management and Transportation after some

Decades of Storage

Design assessment and approval of transport package designand safety evaluation in storage licensing should be linkedeffectively, ideally in an integrated, holistic approach

Permanent validity of transport package design approval certificate is the best measurefor industry and authorities of constraint towards stable control and the safety case`sstate-of-the-art improvement; in case of technical or regulatory changes correctiveactions before transport are justified

International cooperation, experience exchange and joint research is highly recommended, e.g. at IAEA joint TRANSSC/WASSC Work, BAM-CRIEPI, BAM-US NRC, US Extended Storage Committees and other cooperative activities

Panel P 7Long-term storage and transport of

spent nuclear fuel; Regulatory issuesThursday Oct. 7th,14:00-15:40

A. ErhardOral Presentation 061Session T 20, Oct. 5thTuesday 16:00-18:00


Drop Test with a KONRAD Container for LLW Disposal

Waste Packages to be disposed of in the German KONRAD Repository

KONRAD Repository for non-heat generating radioactive Waste (a former iron ore mine, currently under construction;

operation start: current estimate 2019)

•Source=http://www.ballon-sz.de


LLW or MLW Disposal Containers recently drop tested by BAM

Yoyushindo Waste-DisposalContainer (Kobe Steel, Ltd.,for Chubu Electric Power Co., Japan)

KONRAD Container Type V (Eisenwerk Bassum)

Mosaik Cask (GNS)

Heavy Concrete ShieldingKONRAD Container Type I

(FZ Karlsruhe)

3m³ ILW Product Container(DAHER LHOTELLIER CSI, France,

for Sellafield, UK)


Mechanical Design Aspects of Cubic Waste Containers

The Problem of Identification of the worst- case Drop Impactof a Cube Container without Impact Limiter

Pre-test Calculations to evaluate the worst-case Drop Positionor Experiences from Drop Test Series with different Attitudes

Considering the Failure Mode

Maximum Stresses/ Potential Fracture(in thick-walled structures very often a horizontal, flat

bottom drop leads to maximum bending stresses)

Maximum Deformations/potential Material Release

(in thin-walled or welded structures very often corner or edge drop impacts lead to maximum lid

area displacements)

Considering the appropriate Target / Foundation


5 m Drop Test according to KONRAD Repository Requirements

U. Zencker Oral

Presention 220

Session T 28Oct. 6th

Wednesday11:00-13:00


Drop Tests with YOYUSHINDO-DISPOSAL Waste Container

BAM performed a series of three 8 m drop tests with a

new Japanese waste container design,

contracted by Kobe Steel, Ltd. who developed them for Chubu Electric Power

Co., Japan

More details on this test program are presented

in a joint paper from Chubu Electric Power Co., Kobe Steel,Ltd.,

and BAM:T. Quercetti

Oral Presentation 367 Session T40, 7th Oct. Thursday 11:00-13:00


Lifting Operation of the RPPAVR Juelich

Dismantling of Nuclear Power Plants


Large Components Transport by Sea Ship

Loading of Steam Generators (KKS)onto MS SYGYN


Large Components Transport by Road and Rail

Steam Generator KWO

Reactor Pressure Vessel KKR

On-site preparation operations; equipped with additional

shielding components (blue).On public transport (under

Special Arrangement) covered by tarpaulins


Mechanical Assessment of Large Components

Only computational Methods are applicable Here: Finite Element Analysis of a 30 cm horizontal Drop

S. KomannOral Presentation 043

Session T 14Tuesday Oct. 5th

11:00-12:40

(Normal Conditions of Transport mechanical Test, in Handling

Position)


2 Steam Generators (KWO)in Europe`s heighestShip Lifting Device (Niederfinow, 36 m)

Large Components Transport by Inland Waterway Vessel

Fotos: NCS

Loading onto a Barge


Storage of large NPP Components

RPV KKR

Reactor Pressure Vessel(RPV) KGR, Block 5

Steam Generators(SGs) KGR

SG KWO

RPVs KGR Block 4Block 3Block 2

Block 1

Containments with Reactor Core

Components KGR

Decay Storage of 6 dismantled RPVs, various Steam Generators and

shielded Core Componentsat ZLN Lubmin, Hall 8 (EWN)


• An immense variety of packages is needed for spent nuclear fuel and radioactive waste management

• Sophisticated methods have to be applied for their development and safety assessment

• Ageing management during interim storage and transportation of spent nuclear fuel (and HLW) after long-term storage will be an important future topic

• More and more containers for LLW and MLW disposal are actually designed and tested

• Transport and storage of large components from the dismantling of nuclear facilities are carried out more often

Conclusions


Acknowledgements: I would like to thank BfS (F. Nitsche), EWN (D. Rittscher), GNS (H. Geiser, R. Nöring), NCS (F. Hilbert), TN-I (S. Compere) and my colleagues from BAM for their support with material for this presentation

THANK YOU VERY MUCH FOR YOUR ATTENTION !

interaction of package design …. bernhard droste patram 2010 plenary october 5, ... the problem of...

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