Presentation is loading. Please wait.

Presentation is loading. Please wait.

Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006.

Published byValerie Stewart Modified over 8 years ago

Similar presentations

Presentation on theme: "Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006."— Presentation transcript:

1 Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006

2 PPCS Model AB FunctionMaterials PPCS Models Model A WCLL Model B HCPB Model AB HCLL Breeding LiPbBlanket Li 4 SiO 4 Blanket Be Blanket (n multiplier) S t r u c t u r e EUROFER Blanket In vessel shield Blanket Divertor In vessel shield HTS LTS Blanket (+ FW) SS 316VV ZrH HTS CuCrZrDivertor W Divertor (armour) WC LTS W alloy Divertor Co o l i ng Water Blanket Divertor VV LTS (cooling) He Blanket Divertor VV Blanket Divertor HTS

3 Model AB: Activation analysis R. Pampin UKAEA/ TW4-TRP-002 D2e, April 2005 ComponentReplacement schedule DivertorEach 2,5 years Blanket (incl. FW and armour)Each 5 years High Temperature ShieldEach 5 years Low Temperature ShieldLife time component (± 29 years) Vacuum VesselLife time component (± 29 years) TF CoilLife time component (± 29 years) ComponentT0T0 + 10 yearsT0 + 50 yearsT0 + 100 years BackFrontBackFrontBackFrontBackFront FW armour2.67E+044.19E+004.67E-028.68E-03 Blanket FW8.77E+041.70E+013.81E-021.04E-03 Blanket Breeder2.72E+023.67E+041.47E-019.41E-012.74E-031.60E-022.21E-043.92E-03 Blanket Manifold7.93E+024.00E+002.09E-021.63E-04 HTS5.85E+023.10E+001.62E-021.01E-04 LTS3.22E+023.07E-012.93E-031.78E-04 VV1.41E-027.23E-044.05E-061.48E-07 TF coil3.17E-081.30E-093.22E-112.56E-11 Divertor1.78E+031.74E+045.60E+003.16E+002.92E-022.82E-021.59E-043.34E-03 Dose rate Sv/h Replacement Schedule

4 Model AB: Activation analysis R. Pampin UKAEA/ TW4-TRP-002 D2e, April 2005 ComponentReplacement schedule DivertorEach 2,5 years Blanket (incl. FW and armour)Each 5 years High Temperature ShieldEach 5 years Low Temperature ShieldLife time component (± 29 years) Vacuum VesselLife time component (± 29 years) TF CoilLife time component (± 29 years) ComponentT0T0 + 10 yearsT0 + 50 yearsT0 + 100 years BackFrontBackFrontBackFrontBackFront FW armour2.67E+044.19E+004.67E-028.68E-03 Blanket FW8.77E+041.70E+013.81E-021.04E-03 Blanket Breeder2.72E+023.67E+041.47E-019.41E-012.74E-031.60E-022.21E-043.92E-03 Blanket Manifold7.93E+024.00E+002.09E-021.63E-04 HTS5.85E+023.10E+001.62E-021.01E-04 LTS3.22E+023.07E-012.93E-031.78E-04 VV1.41E-027.23E-044.05E-061.48E-07 TF coil3.17E-081.30E-093.22E-112.56E-11 Divertor1.78E+031.74E+045.60E+003.16E+002.92E-022.82E-021.59E-043.34E-03 Dose rate Sv/h Replacement Schedule

5 Time Scale Storage after irradiation Recycling of components separation recycling of materials refabrication and testing Storage awaiting reuse Reuse Stage 1: Temporary storage over a time period of maximum 5 years. The storage will be performed in the fusion plant and its major goal is to reduce the dose rate with 1 order of magnitude. Stage 2: Interim storage over a period of 100 years. The major goal for this on site storage is to reduce the dose rate (a few orders of magnitude) in order to perform off-site transportation. Stage 3: Final disposal (off site). Reference: A. Natalizio (ENSEC); In-vessel component storage, EFDA Task TW2-TRP-PPCS17 – Deliverable 4, dd. 10-01-2003 Separation & recycling of materials (1 year). Refabrication & testing (1 to 2 years) Replacement scheme

6 Simulation of limits for HOR Limits defined in the past: 1000 Gq/g => 4 µSv/h => 6,4 mSv/y 10 µSv/h => 16 mSv/y (full exposure = 1600 h) Limits are very conservative (they meet the ICRP norm for the operators) The goal must not be to increase the limits (ALARA) A simulation with a reduced exposure confirms that materials must not be classified immediately in remote handling recycling if one applies: Shielding Reduced exposure Other measures to reduce the exposure of the operators First conclusion: 1.The limit for Hands On Recycling has to be kept at 10 µSv/h 2.Materials with a dose rate above 10µSv/h must not directly be classified as remote recycling

7 Simulation of limits for HOR Other remarks: 1.Using dose rates for limits between categories starting from HOR is much more logical than using specific activities. 2.On the contrary clearance based on 1 µSv/h has no sense, since pure beta-emitting isotopes can still exceed clearance limits. Therefore the principle of clearance index should be applied for those materials 3.Confinement of the workspace is inevitable, due to the Tokamak dust, Tritium…)

8 Remote Handling Facilities ► Dose rates of fusion components are acceptable for existing facilities ► The 5 years of temporary storage will reduce the dose rates of the components. ► But! What about build up after a second irradiation cycle ► The needed services are very specialised (testing and fabrication), precision ± 10 µm, ► Up to now only simple products were fabricated (melting) ► Confinement is unavoidable to protect the operators from internal contamination

9 Fusion classification

10 New proposal for Classification SRM is subdivided into two groups  Hands on recycling (dose rate up to 10 µSv/h)  Shielded recycling (dose rate between 10 µSv/h and 2 mSv/h) CRM + PDW becomes one group Remote Recycling (above 2 mSv/h) NAW (Clearance) is not defined by the dose rate of the materials but by the Clearance index. Clearance Ic < 1

11 Report: Precondition of the dose rate limits for recycling TW5-TSW-001 D2 SCKCEN: R-4377, 276-06-06, L. Ooms, S. Boden, S. Leblanc Draft available, final report after today’s discussion

Download ppt "Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006."

Similar presentations

Japan/US workshop on Fusion Power Plants, with EU participation, 11-13 January 2005, Tokyo PPCS Safety and Environmental Analysis presented by Neill P.

Japan/US workshop on Fusion Power Plants, with EU participation, January 2005, Tokyo PPCS Safety and Environmental Analysis presented by Neill P.
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.

1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
1 RADIOACTIVE WASTE MANAGEMENT (PART 1) A RAHMAN RWE NUKEM Ltd (UK)

1 RADIOACTIVE WASTE MANAGEMENT (PART 1) A RAHMAN RWE NUKEM Ltd (UK)
PhD studies report: FUSION energy: basic principles, equipment and materials Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.

PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
EPICS Collaboration Meeting – Aix-en-Provence - 1.-3. June 2010 Page 1 ITER welcomes EPICS WD Klotz ITER int. Organiztion That’s me.

EPICS Collaboration Meeting – Aix-en-Provence June 2010 Page 1 ITER welcomes EPICS WD Klotz ITER int. Organiztion That’s me.
A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments:

A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments:
Fusion Power Plant Licensing and Waste Management by Antonio Natalizio for Presentation at the 9 th Course on Technology of Fusion Reactors at Erice (Monastero.

Fusion Power Plant Licensing and Waste Management by Antonio Natalizio for Presentation at the 9 th Course on Technology of Fusion Reactors at Erice (Monastero.
Associazione EURATOM ENEA sulla Fusione By Aldo Pizzuto Comparison of breeder blanket Design 9th Course on TECHNOLOGY OF FUSION TOKAMAK REACTORS – Erice,

Associazione EURATOM ENEA sulla Fusione By Aldo Pizzuto Comparison of breeder blanket Design 9th Course on "TECHNOLOGY OF FUSION TOKAMAK REACTORS" – Erice,
Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop 24-25 April 2005 M. S. Tillack.

Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop April 2005 M. S. Tillack.
Update of the ARIES-CS Power Core Configuration and Maintenance Presented by X.R. Wang Contributors: S. Malang, A.R. Raffray and the ARIES Team ARIES.

Update of the ARIES-CS Power Core Configuration and Maintenance Presented by X.R. Wang Contributors: S. Malang, A.R. Raffray and the ARIES Team ARIES.
ARIES Meeting April 22-23, 2002 U. Wisconsin, Madison Work performed under the auspices of the U. S. Department of Energy by University of California Lawrence.

ARIES Meeting April 22-23, 2002 U. Wisconsin, Madison Work performed under the auspices of the U. S. Department of Energy by University of California Lawrence.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT C L O S E S U P P O R T U N I T G A R C H I N G page 1 of 31 Overview of Reactor Studies in Europe David Maisonnier.

EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT C L O S E S U P P O R T U N I T G A R C H I N G page 1 of 31 Overview of Reactor Studies in Europe David Maisonnier.
Safety Considerations for the EU DCLL DEMO Blanket Dario Carloni 2nd EU-US DCLL Workshop 14-15th November 2014 UCLA.

Safety Considerations for the EU DCLL DEMO Blanket Dario Carloni 2nd EU-US DCLL Workshop 14-15th November 2014 UCLA.
Oxidation of Graphite Walls: Preliminary Results from SOMBRERO Safety Analysis S. Reyes, J. F. Latkowski Lawrence Livermore National Laboratory Laser IFE.

Oxidation of Graphite Walls: Preliminary Results from SOMBRERO Safety Analysis S. Reyes, J. F. Latkowski Lawrence Livermore National Laboratory Laser IFE.
Seminar: Safety in Nuclear Fusion Plants - La Sapienza University (Rome) – 24 April 2015 Design Basis Accidents (DBA) M. T. Porfiri – ENEA UTFUS-TECN (Frascati)

Seminar: Safety in Nuclear Fusion Plants - La Sapienza University (Rome) – 24 April 2015 Design Basis Accidents (DBA) M. T. Porfiri – ENEA UTFUS-TECN (Frascati)
AL FURAT PETROLEUM CO. NORM MANAGEMENT SYSTEM

AL FURAT PETROLEUM CO. NORM MANAGEMENT SYSTEM
Bapetco NORM Control Case Study IDENTIFY ASSESS CONTROL & RECOVERY.

Bapetco NORM Control Case Study IDENTIFY ASSESS CONTROL & RECOVERY.
H IGH L UMINOSITY LHC WP1 - CERN S AFETY R EQUIREMENTS Stefan Roesler - Phillip Santos Silva – Ralf Trant EDMS# 1141248 HSE Unit April 2011.

H IGH L UMINOSITY LHC WP1 - CERN S AFETY R EQUIREMENTS Stefan Roesler - Phillip Santos Silva – Ralf Trant EDMS# HSE Unit April 2011.
FNSF Maintenance and Research Strategy Siegfried Malang and Mohamed Abdou FNST Meeting held at UCLA, August 3, 2010.

FNSF Maintenance and Research Strategy Siegfried Malang and Mohamed Abdou FNST Meeting held at UCLA, August 3, 2010.
Maintenance Schemes for a DEMO Power Plant and related DCLL Designs Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University.

Maintenance Schemes for a DEMO Power Plant and related DCLL Designs Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University.

Similar presentations

Ads by Google