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A New Repository Waste Form:Graphite-Carbon High-Level Waste HTGR Fuel Processing and Waste Forms Charles W.. The HTGR Fuel Micro Spheres are Embedded in a Larger Graphite Matrix Annular

Trang 1

A New Repository Waste Form:

Graphite-Carbon High-Level Waste

(HTGR Fuel Processing and Waste Forms)

Charles W Forsberg, Guillermo D Del Cul, Barry B Spencer, and Emory D Collins

Oak Ridge National Laboratory P.O Box 2008; Oak Ridge, TN 37831-6179 Tel: (865) 574-6783; E-mail: forsbergcw@ornl.gov

Session: Waste Form—II: Source Term Room: Houston 2: Time: 8:30 a.m.

2003 International High-Level Radioactive Waste Management Conference

Las Vegas, Nevada Tuesday April 1, 2003

The submitted manuscript has been authored by a contractor of the U.S Government under contract DE-AC05-00OR22725 Accordingly, the U.S Government retains a nonexclusive, royalty-free license to publish or

reproduce the published form of this contribution, or allow others to do so, for U.S Government purposes File name: HTGR.Waste.2003.HLW.Conference

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High-Temperature Gas-Cooled Reactor (HTGR) Fuel Is Different Than

Light-Water Reactor (LWR) Fuel

80.0% Graphite Block

94.5% C

8.1% Coated Particle Fuel 2.5% Fuel

11.9% Fuel Stick Carbon 3.0% SiC

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The HTGR Fuel Micro Spheres are

Embedded in a Larger Graphite Matrix

Annular Coolant

Channel Fuel Rod Fuel HandlingHole

Fuel Compact

Graphite Sleeve

High Density PyC

0.92 mm

SiC Low Density PyC

Fuel Block

360 mm

580 mm

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Micro-Sphere Cross Section

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Differences In SNF Composition Suggest Different Final Waste Forms

Trang 6

Early (1970s) Designs of HTGR Processing Facilities Burned the

H2O ( 3 H) Iodine ( 129 I)

Krypton ( 85 Kr) Carbon Dioxide ( 14 CO2)

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Later (mid 1970s) Designs of HTGR Processing Facilities

03-047

H2O ( 3 H) Iodine ( 129 I) Krypton ( 85 Kr) Calcium

Carbonate ( 14 C) HLW Glass

(Option)

SiO2SNF

Product

- Fissile

- Fertile

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Conclusions From 1970s Processing

Studies and Path Forward

Graphite with 14 C could not be burned and

release to the atmosphere

HTGR processing is very expensive because

of the graphite waste management issues

Need to consider new approaches

Two approaches identified

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Approach A Burn Graphite and Sequester Carbon Dioxide

(Use Greenhouse Gas Sequestration Research; Option Requires Appropriate Site)

03-048

H2O ( 3 H)

CO ( 14 C)

Iodine ( 129 I) Krypton ( 85 Kr)

HLW Glass

Deep Well Injection with or without Cement

SiO2SNF

Product

- Fissile

- Fertile

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H2O ( 3 H) Iodine ( 129 I) Krypton ( 85 Kr) Graphite ( 14 C, 36 Cl) Graphite-Carbon High Level Waste Form (GC-HLW)

Approach B: Do Not Burn Graphite

(Applicable to Any Site)

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Carbon Waste Volume Depends On the

Waste Form for 14 C Wastes

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Fuel Compact

Crushed Fuel

Nitric Acid

Acid Solution

Fissile Materials

Organic Binder

HLW Slurry

Aqueous

Dissolver Residues Denitrate

Reagent

HLW

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The First Step Is the Mechanical Separation of

Fuel Sticks From the Graphite Block

Annular Coolant

Channel Fuel Rod Fuel HandlingHole

Fuel Compact

Graphite Sleeve

High Density PyC

0.92 mm

SiC Low Density PyC

Fuel Block

360 mm

580 mm

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Fuel Compact

Crushed Fuel

Nitric Acid

Acid Solution

Fissile Materials

Organic Binder

HLW Slurry

Aqueous

Dissolver Residues Denitrate

Reagent

HLW

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Carbon-Graphite Waste Forms Have The Potential For Outstanding Performance

Yucca Mountain examined graphite waste packages because of chemical durability

Oxidation rates extremely low

Low permeability (if appropriately treated)

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Status of Graphite/Carbon Waste Form

Graphite industry experience in forming

graphite/carbon materials

Nuclear industry experience in graphite

treatment

decommissioning graphite reactors (Reduce permeability of final waste form)

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Experimental program planned

Waste form may be applicable to other waste streams

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Backup Slides

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The HTGR Fuel Is Primarily Carbon

Composition (wt%) Function (wt%)

80.0% Graphite Block

94.5% C

8.1% Coated Particle Fuel 2.5% Fuel

11.9% Fuel Stick Carbon 3.0% SiC

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Historical Approach To Processing

HTGR Spent Nuclear Fuel

Remove carbon from fuel by burning

Use traditional (LWR) fuel processing

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Carbon Is the Preferred Waste Form

(If Technically Feasible)

Options

Density of carbon in waste forms determines waste volumes

oxygen, high volume option)

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Calcium Carbonate ( 14 C) SNF

SiO2

Iodine ( 129 I) Krypton ( 85 Kr) SNF Graphite (14C, 36Cl)

HLW

H2O ( 3 H) Iodine ( 129 I) Krypton ( 85 Kr) SNF

Graphite ( 14 C, 36 Cl) GC-HLW

H2O ( 3 H)

CO ( 14 C)

Iodine ( 129 I) Krypton ( 85 Kr) SNF

HLW Glass

Deep Well Injection SiC

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