IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Borehole drilling.

Slides:



Advertisements
Similar presentations
CONSTRUCTION DRILLING INC.
Advertisements

International Atomic Energy Agency IX.4.3. Waste management.
Soil & Site Investigation
CONSTRUCTION OF SOIL NAILING WALLS
GROUNDWATER CONTROL.
UNRESTRICTED / ILLIMITÉ National approach and experience on disposal of Intermediate Level Waste - Canada IAEA ILW Disposal workshop Vienna Sept
Generic Operational Safety Assessment (GOSA) Workshop on the Application of the IAEA Methodology and Safety Assessment Framework (SAFRAN) Tool for the.
How to Build a Groundwater Model Activity Source Created by the USA Groundwater Foundation; modified from the Science Olympiad event, Awesome Aquifers.
Foundations. Foundation supports weight of structure –Includes soil and rock under foundation –Building construction described by foundation type Slab.
Yucca Mountain Deep Repository Michael Hynd. Yucca Mountain Repository Proposed Deep Geological Repository Storage facility for spent fuel and high-level.
Presentation on recent IAEA activities on RWM Y. Kumano WES / NSRW
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.7 Commissioning Geoff Vaughan University of Central.
Gauges and well logging
Regulatory Body MODIFIED Day 8 – Lecture 3.
The Future of Nuclear Waste Management, Storage, and Disposal Thanassi Lefas 26 November 2008 ChE 359 Energy Technology and Policy.
Safe and secure management of sealed radioactive sources in Ghana: status of the borehole disposal project G. Emi-Reynolds, E.T. Glover, M. Nyarku*, P.
Posiva Oy Olkiluoto Eurajoki Puh. (02) 8372 (31) faksi (02) DOPAS Demonstration of Plugs and Seals Posiva Plug Experiment POPLU at URCF.
Monitoring Well Post-Installation Consideration By: Pierre-Orly Dupont.
Authorization and Inspection of Cyclotron Facilities Authorization for the Decommissioning of the Facility.
IAEA International Atomic Energy Agency Roger Seitz Addressing Future Human Actions for Safety Assessment Summary from CSM on Human Action And Intrusion.
John N. Dougherty, PG Lisa Campbell, PG EPA Region 2, New York City
TEAM 1 NONAMECOUNTRY 1SU RUI (LEADER)CHINA 2TENG IYU LIN (PRESENTER)MALAYSIA 3MUHAMMAD TARIQ AZIZ (RAPPORTEUR)PAKISTAN 4NORAISHAH PUNGUTMALAYSIA 5MOHAMMAD.
Landfill. ESSENTIAL COMPONENTS 7 essential components are: (a) A liner system at the base and sides of the landfill which prevents migration.
TM Technical Meeting on the Disposal of Intermediate Level Waste
Decision making process / basic options assessment Mercury Storage and Disposal LAC Two Countries Project Gustavo Solórzano Ochoa, Consultan t Montevideo,
Site Investigation and Storage Structure Sizing CNMP Core Curriculum Section 4 – Manure Wastewater Storage and Handling.
08 October 2015 M. Ammar Mehdi Introduction to Human Resource Management & SSG-16 Actions 4 th Steering Committee on Competence of Human.
IAEA International Atomic Energy Agency David Bennett (David 14 – 18 December 2014 JAEC, Amman, Jordan National Policy and Strategies.
Global Energy Security Forum Miami, Florida March 26, 2013 Mark K. Boling President HYDRAULIC FRACTURING OPERATIONS: SEPARATING FACT FROM FICTION.
International Atomic Energy Agency IX.4.6. Management of disused sealed sources Technical options and safety aspects.
Nicolas Solente Workshop on Regulatory Requirements to Ensure Safe Disposal of Disused Sealed Sources for Operators and Regulators Amman, JORDAN 7-11 April.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
David G Bennett December 2014
SAFRAN Upgraded to support the implementation of the Borehole Disposal Concept Rodolfo Avila, Facilia AB.
Clear thinking on Nuclear: Waste disposal 1.One site for high-level radioactive waste is easier to monitor, regulate, and secure 2.A repository will provide.
International Atomic Energy Agency Roles and responsibilities for development of disposal facilities Phil Metcalf Workshop on Strategy and Methodologies.
Groundwater Water Table Recharge Groundwater Hydraulic Gradient
International Atomic Energy Agency Regulatory Review of Safety Cases for Radioactive Waste Disposal Facilities David G Bennett 7 April 2014.
AuthorizationAuthorization. Authorization Objectives To provide understanding of the authorization process and the procedures for its implementation.
Safety-related Issues for the Disposal of Intermediate Level Waste (ILW) Dr. Jürgen Wollrath Federal Office for Radiation Protection (BfS) Department Safety.
Waste and site related issues Fredrik Vahlund SKB.
International Atomic Energy Agency IX.4.2. Principles of radioactive waste management Basic technical management solutions: concentrate and contain, storage.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Environmental.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Containment and.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Borehole Sealing.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Procedures and.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Overview of radiation.
Regional Workshop on Waste Management and Safe Disposal of Radioactive Waste - Tunis, Tunisia; March 2014 Management of Radioactive Waste in Jordan.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Siting Strategies.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Waste Acceptance.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Requirements for.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Program and Quality.
IAEA International Atomic Energy Agency Roger Seitz Potential Working Groups.
EXERCISE 1 GROUP : OPERATOR. Safety Case : Post Closure Of A Disposal Facility Introduction  The facility is situated in Vaalputs, South Africa.  It.
International Atomic Energy Agency V. Nys Definition and practical application of demonstration of operational and long-term safety for predisposal RWM.
Hydraulic Fracturing (Fracking)
Expert Review of the Licensing Documentation of the Centralized Facility for Long-Term Storage of Disused Sealed Radiation Sources Oleksii Tokarevskyi.
1 Waste volumes and categories Low active waste Medium active waste High active waste Short livedCategory A Category C Long livedCategory B Category C.
Site characterization and data requirements for implementing the BDC
Sustaining Cradle-to-Grave Control of Radioactive Sources (INT-9182) Meeting on the development, revision and implementation of the safety case and safety.
Andrzej Kotyrba Central Mining Institute Katowice, Poland
Module Planned exposure situations Public exposure (GSR Part 3)
Sustaining Cradle-to-Grave Control of Radioactive Sources (INT-9182) Workshop on implementation of a national cradle-to-grave control system for radioactive.
Safety and Security of Radiation Sources
Factsheet: Proper Permanent Well Abandonment for Virginia Coastal Plain Wells VDH DEQ What is.
The Future of Nuclear Waste Management, Storage, and Disposal
Addressing Future Human Actions for Safety Assessment
SAFRAN Upgraded to support the implementation of the Borehole Disposal Concept Rodolfo Avila, Facilia AB.
Presentation transcript:

IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Borehole drilling and completion, repository design

IAEA Outline/ Contents Main components of the BDC design and their safety functions Adapting the generic design to a specific site Drilling and completing a disposal borehole 2

IAEA Main references 3 TECDOC 1644 Requirements for disposal Guidance for borehole disposal Technology of the BDC

IAEA Main components of the BDC and their safety functions 4

IAEA Borehole Design 1 102

IAEA 1 m Ground surface Closure zone, minimum 30 metres Anti-intrusion plate Casing removed over top two metres Backfill with native soil Disposal zone Concrete closure seal GEOSPHERE

IAEA Components disused sources capsule Container backfill Container Repository backfill Casing Centraliser Borehole grout Geosphere Container to container spacing of 1m Anti-intrusion plate immediately above the waste A closure zone with a minimum length of 30 metres concrete closure seal Casing removal (top 2m) 7

IAEA Components and safety functions 1 8 COMPONENT SAFETY FUNCTION/ DESIGN RATIONALE Disused sealed sourcesNone – is assumed that the radionuclides in the sealed sources are free to migrate Capsule Container Capsule and container are made from corrosion- resistant stainless steel which provide absolute physical containment for a time that is dependent on the rate of corrosion The capsule and container are designed to be easily handlable Container backfill Repository backfill Borehole grout All these materials are cementitious. This produces high pH conditions that reduce the rate of container and capsule corrosion. The cement also provides surfaces on which radionuclides can sorb.

IAEA Components and safety functions 2 9 COMPONENT SAFETY FUNCTION/ DESIGN RATIONALE CasingFacilitates operation by supporting the borehole wall, excluding groundwater, providing a smooth surface to prevent snagging when emplacing waste packages It has no long-term safety function Casing centraliserFacilitates operation by ensuring that the borehole is close to vertical Container to container spacing Provides adequate concrete to provide pH buffering; provides dilution by spreading out any contaminant plume Anti-intrusion platePrevents inadvertent drilling into the disposal zone Closure zone minimum 30mProvides isolation of the waste by placing it out of reach of normal deep excavation activities eg roads, foundations of buildings

IAEA Components and safety functions 3 10 COMPONENT SAFETY FUNCTION/ DESIGN RATIONALE Concrete closure sealSeals the borehole and provides isolation of the wastes through its physical presence and containment of radionuclides by protecting the waste packages from damage and corrosion Casing removal (top 2m) A security measure that prevents unauthorized access to the waste by hiding the borehole location from sight. The precise location will be known to the authorities who, in any event, would have equipment that was capable of finding it GeosphereProvides isolation of the wastes from the human environment and containment of radionuclides by protecting the waste packages from damage and corrosion. In the event of radionuclide migration from the facility, it will also provide retardation allowing more time for radionuclides to decay

IAEA Influences on the site-specific design 11

IAEA Influences on facility design 12 Inventory Regulation/ legislation Site properties Fixed parameters (Waste package design, MHC etc) Economic/ practical issues Facility Design Safety assessment

IAEA Economic and Practical issues Choice of site Remoteness of the site/ access to transport and utility infrastructure Availability of suitably qualified contractors with appropriate equipment Availability of construction and emplacement materials eg casing, cement, sand, water Site properties (groundwater, weathered zone, complexity, topography…) Stakeholder and Regulatory interactions 13

IAEA Regulation/ legislation Determines the safety standards to be met May also prescribe other issues eg Format of the safety case or safety assessment Who is permitted to design the facility The need (or not) for retrievability Use of the Model Regulations will anticipate many of the questions to be answered Licensee will need to have a very good understanding of how regulations will impact on what is planned 14

IAEA Inventory Compared to (say) disposal of NPP wastes, inventory characterization of disused sealed sources is straightforward Key parameters to be determined for each source: Identification of radionuclide/ nuclear reaction/ emissions Activity at specified date Physical size of source to be disposed Current storage and handling arrangements / means of retrieval from store / weight Means of removal of bare source from operating shield Need for shielding during conditioning/ containerization HENCE relevant to design: Number of waste packages -> number of boreholes Need (or not) for MHC and remote handling, lifting equipment etc 15

IAEA Inventory and decay 16

IAEA Important Site properties Depth to water table Existence of near-surface weathered rocks Separation of near-surface and deep water bodies Rate of surface erosion/ geomorphology Properties of potential host geology Structural Geomechanical Geochemical Etc –see previous lecture 17

IAEA Adapting the generic design to a specific site 18

IAEA Important design issues to be determined 19 ISSUEHOW DECIDED Which site?Governmental or community decision Where on the site?Avoid large faults, nearby surface facilities How many boreholes, what depth?Design optimization based on the inventory and the site properties – see later New borehole or modify existing characterization borehole? Largely an economic and practical issue

IAEA Borehole design optimization 1 20 First decide the length of the disposal zone(s) from: 1. Number of packages – dependent on number and type of sources 2. Package to package spacing – reference design has 1m spacing but could be half this Package to package spacing

IAEA Cro ssla nd Con sulti ng -30m Required length of disposal zone Water table Dry season Wet season Total b/h depth determined by disposal zone length plus 30m or max depth of water table (whichever is greater) Borehole design optimization 2

IAEA 22 Aquiclude Aquifer Min. depth of disposal 30m Aquifer depth 70m Required b/h depth 100m Near-surface weathered rocks Groundwater 20m Phreatic surface Borehole Design Optimization 3

IAEA Drilling and completing a disposal borehole 23

IAEA 24 Drilling BDC designed to use techniques that are widely available Borehole diameter 0.26m minimum – is typical of boreholes used for groundwater abstraction Would normally used rotary air percussion drill Not necessary to core the disposal borehole but retain samples of chippings for every metre of borehole

IAEA Construction - Drilling 25

IAEA 26 Construction 1 Borehole to be cased (lined) to full depth

IAEA 27 Construction 2 Borehole to be cased (lined) to full depth Insertion of mild steel or HDPE casing with centralizers

IAEA 28 Construction 3 Borehole to be cased (lined) to full depth Mild steel or HDPE tubing Concrete plug at the base (placed using tremmie pipe)

IAEA Casing insertion and grouting 29

IAEA 30 Construction 4 Borehole to be cased (lined) to full depth Mild steel or HDPE tubing Concrete plug at the base (placed using tremmie pipe) Grouting of annulus (ditto) Checks and hold point to confirm borehole is correctly built and ready for operation

IAEA Summary Main components of the BDC design and their safety functions Containers and capsule, backfill, casing etc Influences on the site-specific design Practical/ regulatory/ inventory/ site properties Adapting (optimizing) the generic design for a specific site Two examples given – one leads to one borehole, the other, two Steps in the construction of a disposal borehole 31

IAEA 32 Thank you!