Paul Humphreys. Gas generation is a fundamental issue in radioactive waste disposal Direct impact on: – Waste processing and packaging – Facility design.

Slides:



Advertisements
Similar presentations
The Mythology of the Back End of the Nuclear Fuel Cycle Allison Macfarlane Program in Science, Technology & Society MIT April 24, 2006.
Advertisements

Corrosion Evaluation of Metallic Materials for Long-Lived HLW/Spent Fuel Disposal Containers – review of years of research B. KURSTEN, SCKCEN (Mol,
Properties of Matter.
Generation of Radioactive Waste Radioactive Waste Management and Disposal NUCP
Chapter 5: GASES Part 2.
D:\data\PowerPoint\Maravic\NCP-EURATOM Meeting - CCAB ppt Slide 1 National Contact Points for EURATOM- Information Exchange Meeting October 16,
Dr Paul Dorfman Nuclear Consultation Group Helsinki, 8 May 2009 High Burn-up Radioactive Spent Fuel.
Use of reference biospheres to prove long-term safety of repositories for radioactive waste Workshop, Berlin, August 2008.
Topics for Today Burning a gallon of gasoline… Where does my gasoline come from?
Mole-Mass and Mole-Volume Relationships
The LUCOEX project has received funding from the European Atomic Energy Community’s 7th Framework Programme (FP7/ ) under the grant agreement No.
Hydrocarbon Fuel Problems Noadswood Science, 2011.
Carbon Cycle! Josh, Josh, Austin, Bethany APES 3rd.
UNRESTRICTED / ILLIMITÉ National approach and experience on disposal of Intermediate Level Waste - Canada IAEA ILW Disposal workshop Vienna Sept
Metal Dusting Calculations Project By Sheldon W. Dean October 22, 2002.
Yucca Mountain High-level Nuclear Waste Repository.
Presentation on recent IAEA activities on RWM Y. Kumano WES / NSRW
History of waste disposal. 2 J.H. Saling and A.W. Fentiman, “Radioactive Waste Management,” Second Edition, (Taylor & Francis, NY  London) 2002.
JNFL Sub-Surface Disposal Plan and Safety Strategy for Relatively Higher LLW Kazuyuki KATO Japan Nuclear Fuel Limited (JNFL) Technical Meeting on the Disposal.
1 RADIOACTIVE WASTE MANAGEMENT (PART 4) A RAHMAN RWE NUKEM Ltd (UK) Name, company and chapter.
Solutions The Solution Process.
SAFESPUR 9/7/08 1 Innovation in Nuclear Decommissioning: New Technologies and Research, SAFESPUR Forum, July 9, 2008 G.R. Elder Bradtec Decon Technologies.
҉ What is nuclear fission? ҉ Nuclear fission is when a nucleus breaks apart due to its divorce. It is the main process used in nuclear power plants to.
Section 2: Nonrenewable Energy
Handling of Future Human Actions in the safety assessment SR-Site Eva Andersson.
TM Technical Meeting on the Disposal of Intermediate Level Waste
Estimation of storage capacity needed or limits. Comparison with existing storage facilities. Lise-Lotte Spontón TW5-TSW-001, D4 Final meeting, TW5-TSW-001.
NDA PhD Bursary Spent Fuel Theme Carwyn Jones, Nuclear Technologies (representing NDA) 25 th August 2015.
Shipwrecks, Corrosion and Conservation Summary Slides PART 4 – Jack Dengate.
Big Blue Marble. Earth’s Systems are: Atmosphere Geosphere Hydrosphere Biosphere.
International Atomic Energy Agency IX.4.1. Sources of radioactive waste Waste types, waste classification, waste characterization.
ILW disposal in the UK Presentation at IAEA TM-45865, September 2013 Cherry Tweed – Chief Scientific Advisor.
Evaluation of the radiological consequences of tritium present in radioactive components from fusion reactors Task TW4-TSW-001-D1b: Waste and decommissioning.
THE CARBON CYCLE AND GLOBAL WARMING
David G Bennett December 2014
Numerical Simulations of Atmospheric Carbonation in Concrete Components of a Deep Geological Intermediate Low Level Waste Disposal NUCPERF 2012 P. Thouvenot.
Characterisation of reactor graphite to inform strategies for the disposal of reactor decommissioning waste Andrew Hetherington (presented by Dr Paul Norman)
1.Issues concerning the Inventory 2.Issues concerning Gases 3.Site considerations 4.Construction Issues 5.Waste Packaging.
Integrated Waste Management Strategy – preparing for SIII NuLeAF – 29 th January 2015.
This project has received funding from the Euratom research and training programme under grant agreement No Improving the geological.
Groundwater Water Table Recharge Groundwater Hydraulic Gradient
Chapter 12 Notes #2. A landfill is a waste disposal facility where wastes are put in the ground and covered each day with dirt, plastic, or both. 50%
Effective Application of Partitioning and Transmutation Technologies to Geologic Disposal Joonhong Ahn Department of Nuclear Engineering University of.
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.
Solutions. A solution is a homogenous mixture of 2 or more substances. The solute is(are) the substance(s) present in the smaller amount(s). What is being.
© 2016 Cengage Learning. All Rights Reserved. 7 Oceanography, An Invitation to Marine Science | 9e Tom Garrison Ocean Chemistry.
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 Requirements for.
Biochemical Oxygen Demand (BOD) and Dissolved Oxygen (DO) 1. Background Information.
IAEA International Atomic Energy Agency TM Technical Meeting to Discuss Human Intrusion and Future Human Actions in relation to Disposal of Radioactive.
The effect of radiation damage by fission fragments on dissolution of spent nuclear fuel Aleksej Popel, PhD candidate Supervisor: Dr Ian Farnan Department.
Structure of a Safety Case (NEA). The Multibarrier Concept each barrier acting passively in concert with the others to isolate, contain and reduce impacts.
Global Warming The level of greenhouse gases in the atmosphere has gradually increased as a result of: Keywords: Oceans, Water Vapour, Photosynthesis,
Chapter 15: Solutions. Solutions Solution – a homogeneous mixture of two or more substances in a single physical state. Solution – a homogeneous mixture.
Core Chemistry Revision To improve understanding of key topics.
Engineering Materials part 1
Report on the outcome from the consultancy
Elements, Compounds and Mixtures
Repository scale two-phase flow migration of 14C in the preliminary design phase of French Cigéo project Eloi Treille, Jacques Wendling Andra, 1/7 rue.
Name: André Rübel Organisation: GRS Date:
Olli Nummi, Fortum, Finland
For more information, please visit the CAST website at:
CArbon-14 Source Term CAST
THE SPHERES OF THE EARTH
Bellringer What is the most basic level of ecological organization? What is the broadest level?
Introduction: IAEA activities / Documents on human intrusion
Chemical Calculations
PAPER NUMBER 98 Disposal project for LLW and VLLW generated from research facilities in Japan: A feasibility study for the near surface disposal of VLLW.
Presentation transcript:

Paul Humphreys

Gas generation is a fundamental issue in radioactive waste disposal Direct impact on: – Waste processing and packaging – Facility design – Radionuclide release Nature and extent of gas generation depends on type of waste and the facility

Gas Generation Release of Radioactive Gases Groundwater Impacts Engineering Impacts Methylated Gases 14 C & 3 H labelled Gases

Microbial Activity Radiolysis/ Radiation/Decay Corrosion MIC Hydrogen Generation Hydrogen Generation Polymer Degradation

Polymeric Waste Components Cellulose IX Resins Plastics/ Rubber Soluble Intermediates Microbial/ Chemical/ Radiolytic Degradation Microbial Metabolism Metals Gas (CH 4, CO 2, H 2 S) Corrosion H2H2

PCM 14 C 222 Rn

International agreement – Multi-barrier concept of disposal LLW, ILW & HLW

Dose assessments calculated Based on travel time back to surface Scenario approach

Radioactive waste disposal sites are evaluated via a safety case – Includes risk assessment modelling based on exposed dose yr -1 Safety cases produced throughout the lifetime of a repository Gas generation issues need to be integrated into a safety case. – Gas generation modelling

GRM – LLWR GAMMON/SMOGG – UK NIREX/NDA T2GGM – Canadian DGR

Polymeric Waste Components Cellulose IX Resins Plastics/ Rubber Soluble Intermediates Microbial/ Chemical/ Radiolytic Degradation Microbial Metabolism Metals Gas (CH 4, CO 2, H 2 S) Corrosion H2H2 Transport

Processing of H 2 has a major impact on model out puts Access to CO 2 key issue

Controlled by corrosion rate 3 TEA processes – H 2 + 2Fe(III) 2Fe(II) + 2H + – 4H 2 + SO H + H 2 S + 4H 2 O – CO 2 + 4H 2 CH 4 + 2H 2 O Hydrogen metabolism key process in controlling repository pressure – 4H 2 = 1H 2 S or – 4H 2 + 1CO 2 =1CH 4

Illustrative calculated results for net rates of gas generation from UILW in higher strength rocks for the 2004 Inventory H 2 dominates CO 2 assumed to be unavailable due to cement carbonation

16

DGR located in low permeability argillaceous limestone

200,000 m 3 of LLW & ILW No HLW or spent fuel

19 Oxygen consumed (in a few years) Water starts to seep into repository Water aids corrosion and degradation of wastes Gas pressure increases Water is forced out into surrounding rock mass Bulk and dissolved gases slowly migrate out into shaft and rock mass Small quantities of dissolved gas (and no bulk gases) reach biosphere over 1 Ma timescales

Wide range of calculation cases considered Including shaft failure cases Peak pressure 7 – 10 MPa (Repository horizon: 7.5 MPa, Lithostatic 17 MPa) Methane is the dominant gas Repository does not saturate over 1 Ma timescale Peak pressure 7 – 10 MPa (Repository horizon: 7.5 MPa, Lithostatic 17 MPa) Methane dominant gas Repository does not saturate over 1 Ma timescale Saturation Pressure

Seepage Gas Pressure Saturated Unsaturated TOUGH 2 Corrosion and microbial processes slow as humidity decreases from 80% to 60% Geosphere Corrosion and microbial processes stop <60%

Availability of CO 2 in a cementitious repository – Major impact on overall gas volumes – Fate of waste derived carbon dioxide Fate and transport of 14 C another area of uncertainty

Substantial quantities of 14 C generated in nuclear power reactors Present in irradiated metal and graphite – Chemical form and chemical evolution major impact on transport. The release of volatile 14 C is assumed to be in the form of methane

` Release Groundwater Gas CH 4 CH 4 CO 2 14 C Dose Calculation Near-Field Geosphere Biosphere