Development of tritium breeder monitoring for Lead-Lithium cooled ceramic breeder (LLCB) module of ITER presented V.K. Kapyshev CBBI-16 Portland, Oregon,

Slides:



Advertisements
Similar presentations
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.
Advertisements

Hongjie Zhang Purge gas flow impact on tritium permeation Integrated simulation on tritium permeation in the solid breeder unit FNST, August 18-20, 2009.
SABR REACTOR CORE & TRITIUM BREEDING BLKT W. M. Stacey Georgia Tech September, 2009.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.
Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1.Outline of blanket development in JAERI 2.Design.
FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.
US TBM Meeting INL, August 10-12, 2005 B. J. Merrill and D. A. Petti Fusion Safety Program Safety and Tritium R&D.
ARIES Meeting General Atomics, February 25 th, 2005 Brad Merrill, Richard Moore Fusion Safety Program Pressurization Accidents in ARIES-CS.
Summary of Recent Neutronics Integral Experiments on C/E M. Youssef UCLA ITER TBM Project Meeting, UCLA, February 23-25, 2004.
Status of safety analysis for HCPB TBM Susana Reyes TBM Project meeting, UCLA, Los Angeles, CA May 10-11, 2006 Work performed under the auspices of the.
Neutronics Issues to be Resolved in ITER Test Blanket Module (TBM)  Demonstration of tritium self-sufficiency for a particular FW/B/S concept  Verification.
Resent Breeding Blanket Experiments - CONTENTS - - Objectives - - Resent breeding design at JAERI - - Brief history of FNS blanket experiments - - Resent.
US ITER TBM Meeting Idaho Fall, Idaho, Aug M Dagher P Fogarty 1.TBM/ITER General Arrangement 2.Equatorial Test port Configuration 3.Test Port.
Y. ASAOKA, R. HIWATARI and K
Accident assessment for DCLL DEMO design Susana Reyes TBM Project meeting, UCLA, Los Angeles, CA March 2-4, 2005 Work performed under the auspices of the.
The effect of the orientations of pebble bed in Indian HCSB Module Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept.
Development of the FW Mobile Tiles Concept Mohamed Sawan, Edward Marriott, Carol Aplin University of Wisconsin-Madison Lance Snead Oak Ridge National Laboratory.
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
Vacuum Photodiodes for Soft X-Ray ITER Tomography Yu.Gott, M.Stepanenko 10th ITPA Meeting, Moscow, 2006.
TBM WG Meeting UCLA, March 2-4, 2005 Brad Merrill/Fusion Safety Program DCLL TBM Safety Update.
Overview of LLCB TBM for ITER Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept. 2011, Portland, USA.
1 Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis Ying, Alice With contributions from M. Narula, H. Zhang,
Fusion-Fission Hybrid Systems
Fusion Blanket Technology
Neutronics Parameters for Preferred Chamber Configuration with Magnetic Intervention Mohamed Sawan Ed Marriott, Carol Aplin UW Fusion Technology Inst.
0 Laser Flash Method for Effective Thermal Diffusivity Measurement of Pebble Beds CBBI-16 Portland, OR, USA Sept. 9, 2011 Mu-Young Ahn 1, Duck Young Ku.
Page 1 of 11 An approach for the analysis of R&D needs and facilities for fusion energy ARIES “Next Step” Planning Meeting 3 April 2007 M. S. Tillack ?
1 Solid Breeder Blanket Design Concepts for HAPL Igor. N. Sviatoslavsky Fusion Technology Institute, University of Wisconsin, Madison, WI With contributions.
1 Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder Concept Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder.
Hydrogen system R&D. R&D programme – general points Hydrogen absorber system incorporates 2 novel aspects Hydrogen storage using a hydride bed Hydrogen.
Design study of advanced blanket for DEMO reactor US/JP Workshop on Fusion Power Plants and Related Advanced Technologies 23 th -24 th Feb at UCSD,
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
Solid Breeder Blanket R&D and Deliverable TBM Costing Kickoff Meeting INL, August 10-12, 2005 Presented by Alice Ying.
Tritium Extraction from a DCLL Blanket Prepared by: Scott Willms (LANL) Collaborators: Brad Merrill (INL), Siegfried Malang (Consultant), Clement Wong.
Overview of Fusion Neutronics Activities at JAERI/FNS in 2004 Presented by T. NISHITANI Japan Atomic Energy Research Institute, Tokai-mura, , Japan.
David Rapisarda CIEMAT 2 nd EU-US DCLL Workshop University of California, Los Angeles, Nov th, 2014.
Study of Processes of Hydrogen Isotope Interaction with Lithium CPS
KIT Objectives in Fusion by 2020 Workshop on the European Fusion Roadmap for FP8 and beyond April 13 – 14, 2011; IPP Garching.
1 Neutronics Assessment of Self-Cooled Li Blanket Concept Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
Copyright by Team 5- Group Document contains personal property from a team effort and Patent Protection will be supported, this is a message of intent.
Base Breeding Blanket and Testing Strategy In FNF Conclusions Derived from Previous FNST Workshop, August 12-14, 2008.
Background information of Party(EU)’s R&D on TBM and breeding blankets Compiled and Presented by Alice Ying TBM Costing Kickoff Meeting INL August 10-12,
An ITER-TBM Experimental Thrust for ReNeW Themes III and IV Neil B. Morley, Mohamed Abdou, Alice Ying (UCLA); Mohamed Sawan, Jake Blanchard (UW); Clement.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
Association Euratom-Cea IEA Tritium and Safety Issues in LL Breeders, June 2007, Idaho Falls J-F. Salavy 1 IEA Implementing Agreement on Nuclear.
Fusion Neutronics Activity at JAERI from October 2000 to September 2001 Peseted by Takeo NISHTANI IEA International Work Shop on Fusion Neutronics The.
IEA IMPLEMENTING AGREEMENT ON NUCLEAR TECHNOLOGY OF FUSION REACTORS International Workshop on Subtask Neutronics Report on ENEA activity in 2004 Paola.
Fuel Cycle Research Thrust Using A Full Fusion Nuclear Environment
1 Discussion with Drs. Kwon and Cho UCLA-NFRC Collaboration Mohamed Abdou March 27, 2006.
Venice, September 21, 2004 K. Seidel,TU Dresden IEA collaboration in fusion neutronics Activities of TU Dresden 1. Activation of fusion reactor materials.
ARIES Meeting University of Wisconsin, April 27 th, 2006 Brad Merrill, Richard Moore Fusion Safety Program Update of Pressurization Accidents in ARIES-CS.
MAIN COMPONENTS  INTODUCTION  PRINCIPLE  CONSTRUCTIONAL DETAILS  PROCESS  ADVANTAGES  DISADVANTAGES  CONCLUSION.
Fusion. Examples ● Fusion is the reaction that produces the energy in the sun.
The tritium breeding blanket in Tokamak fusion reactors T. Onjun1), S. Sangaroon2), J. Prasongkit3), A. Wisitsorasak4), R. Picha5), J. Promping5) 1) Thammasat.
HARNESSING FUSION POWER POWER EXTRACTION Power Extraction Panel Preliminary Research Thrust Ideas Robust operation of blanket/firstwall and divertor systems.
Thermal-hydraulic analysis of unit cell for solid breeder TBM
US Participation in the
Description of Thin Liquid Wall Protection w/Porous Walls
DCLL TBM Reference Design
Can We achieve the TBR Needed in FNF?
Toroidal Fusion Shielding Design Project
VLT Meeting, Washington DC, August 25, 2005
«FC-FNS» simulation code
A. Vertkov et al., SC “Red Star”, Moscow, Russia
TRL tables: power conversion and lifetime
Nuclear Analyses for two “Look-alike” HCPB Blanket Sub-modules for Testing in ITER Mahmoud Z Youssef UCLA Presented at ITER-TBM4 Meeting, UCLA, March 2-4,
Presentation transcript:

Development of tritium breeder monitoring for Lead-Lithium cooled ceramic breeder (LLCB) module of ITER presented V.K. Kapyshev CBBI-16 Portland, Oregon, September, 2011 Portland, Oregon, September, 2011

OUTLINE 1. Problem of Tritium Breeding Ratio (TBR) monitoring 2. Fusion Reactor Facility for Tritium Breeder Monitoring 3. R&D

Tritium Breeding Ratio (TBR) of DEMO / ITER The most important tritium cycle parameters : - tritium breeding ratio (TBR), - amount of tritium in the reactor, ТВR = Q reactor / Q plasma (1) Q reactor – tritium amount breaded in reactor blanket and plasma Q plasma - tritium amount burned-up in plasma. Q reactor = Q TBZ +Q DD

Conception of TBR monitoring using Test Breeding Modules of ITER Conception of TBR monitoring of reactor includes: - measurements of numerator and denominator in formula (1), - calculation booth. Experimental definition of tritium amount burned in plasma (denominator in formula (1)) is proposed to do by measurement of neutron number arisen in result of (D-T) reaction. Numerator demonstrates tritium breeder in a tritium breeder zone (TBZ) of reactor blanket under neutron interaction with lithium and beryllium isotopes

Problem of TBR Precision Measurement TBR for the DEMO with ceramic blanket ~1.05. Error ( Δ ) of TBR measurement according (1): Δтв R = Δrеакtоr + Δplаsmа Δrеакtоr ~Δ TBZ The most accuracy measurements can be done in case of tritium breeder and neutron detectors location in TBZ for short time and follow remove of its from TBZ after plasma pulse, delivery to an analytical laboratory for analyzing. Q reactor

Fig. 1 Conception of TBR monitoring using TBM of ITER 1- TBZ of TBM, 2- Tritium Breeding Canals (TBC) for samples, 3- casks with samples under irradiation, 4-in-put chamber, 5- transporter room, 6- tritium laboratory delivery of casks with samples; extraction of irradiated casks

Fig. 2. Location of capsules with material samples in cask This is a capsule presenting hermetic cylinder cask closed by plugs to each end.

Table 1. Content of samples in casks № cask Tritium breeder material Isotope ratio ( 6 Li / 7 Li) Absorbers of thermal neutrons 1Li 2 CO 3 natural– 2Li 4 SiO 4 natural+ 3Li 4 SiO 4 natural– 4Li 4 SiO 4 ~ 1– 5Li 4 SiO 4 ~ 1+ 6Li 4 SiO 4 ~ 10– “+” –yes, “-“- no

2. Pneumatic and mechanical systems of transportation the casks to the Module The canal (TBC) contains three parts: - “operation” part with length ~ 0.55 m locating in TBM; - part between TBM back plate and operation room; - “leader” part with length ~ 0.5m for loading and unloading casks. Transportation of the cask to the Module and back is proposed to do by two methods: mechanical with gas cooling and pneumatic.

2.1 Initial Design of Pneumatic Tritium Breeding Canal (TBC) The canal (TMC) for irradiation materials is thought as two coaxial pipes (Ø 14х1 mm and Ø 20х1 mm). Coolant movement through the canal is possibly both straight and reveres. Fig. 3. Longitudinal section of TBC 1-beryllium plug, 2-container, 3-beryllium multiplier, 4-separation elements, 5-rib of TBSM case, 6-back plate of TBM case, 7-out side of canal pipe, 8-bellow, 9-frame, 10-inner pipe of canal, 11-shield plug, 12-armored bellows, 13-heat shield, 14-biological shield, 15- fastening unit of canal,16-union, 17-adapter, 18-load chamber, 19- fingered bushing, 20-bolt, 21-transporter.

Fig. 4 Conceptual diagram of monitoring breeder tritium system with gas circulator to provide necessary temperature mode of lithium detector operation 1-channel of tritium breeder monitoring, 2-commutator of gas flow, 3-system of gas circulator, 4-pneumatic deliver system of samples to channel, 5-monitoring tritium system in CCTB, 6-pressure regulator, 7-gas cylinder, 8-heat exchanger, 9-circulator pump, 10- vacuum pump, 11-tank, 12-system of initial gas process and monitoring of tritium content in the gas, 13-system of radiation safety

TMC Fig.11 Tritium Monitoring Canal in Ceramic-Eutectic TBM L radial =450mm.

Table 4 Tritium breeder in detectors of TMC placed in core of TBM’s cap (t=3*10 3 c) Bk/detector detector Li-6 content _________________________________________________________ 9.24E+04 Eutectic 7.4% 3.62E+06 Eutectic 50% 3.12E+04 Eutectic 90% 2.60E+04 Li 4 Si O 4 7.4% 3.02E+04 Li 2 CO 3 7.4%

R&D 1. Laboratory devices for investigation of pneumatic systems 2. Development: - cask and capsule, - analytical methods for measurement of tritium breaded in lithium detectors under irradiation in IVV-2M nuclear reactor 3. Selection and irradiation of neutron detectors in IVV-2M nuclear reactor 4. Irradiation of the cask and capsule in IVV-2M

Development and test of Tritium Breeding Ratio (TBR) system monitoring -laboratory facility for parameters investigation of sample deliver to TBM (pneumatic method, length=9m, T(active zone) = 200  С) methods and analytical systems for measurement of tritium breaded in the samples (Li 4 SiO 4, Li 2 CO 3, tritium content~10 3 bq/s) -development of nuclear reactor facility for TBR system monitoring test (T=200  С, neutron flux ~ 2*10 14 n/sm 2, t (neutron irradiation)~10min)

Development of liquid scintillation method Li 2 CO 3 Dierckx’s method (1973) Δ Li-sample = 6-7% Li 4 SiO 4 Verzilov’s et all method (2005) Li 4 SiO 4 +4HA=4LiA+SiO 2 ↓+2H 2 O HA=mix(CH 3 COOH; HNO 3 ) Δ Li-sample = 10 %

Hydrogen isotope permeation through structural materials Laboratory facility for investigation of hydrogen permeation through structural materials (T=  С P(H2/D2~0,1 МПа, ferritic SS 10X9MB9,austenitic SS ) Development of reactor experimental facility for investigation of tritium release through structural materials under reactor irradiation (T=  С, neutron flux ~ n/sm 2 )

CONCLUSION 1. Conception of tritium breeding ratio measurement and irradiation of material samples has been proposed to irradiate of the samples and to estimate tritium breeder rate in ITER TBM by experimental method under ITER normal operation. 2. Canal design is developed for irradiation of ceramic lithium, neutron detector, material samples during plasma pulse in ITER and for fast its transportation to analytical laboratory. 3. Accuracy of tritium content measurement for lithium carbonate and lithium orthosilicate is 7 % and 10%.

1. Tritium Breeding Ratio (TBR) of DEMO / ITER The most important tritium cycle parameters : - tritium breeding ratio (TBR), - amount of tritium in the reactor, tritium balance - radiation safety parameters. ТВR = Q reactor / Q plasma (1) Q reactor – tritium amount breaded in plasma and in reactor blanket Q plasma - tritium amount burned-up in plasma.

TBR for the DEMO with ceramic blanket ~1.05. Sufficiently accuracy definition of tritium amounts breaded in a module (numerator in (1)) isn’t really possibly by continue measurements in purge-gas system. The most accuracy measurements can be done in case of tritium breeder and neutron detectors location in TBZ for short time and follow remove of its from TBZ after plasma pulse, delivery to an analytical laboratory for analyzing. Detectors can be located for one plasma pulse period

Accuracy of tritium content measurement in samples Δтв R = Δrеакtоr + Δplаsmа Δrеакtоr = Δ TBZ + Δd,d (D,D) (Dd,d) Δd,d = Δd,t * (Sd,d( t plasma )/ Sd,t( t plasma)) Δ TBZ ~ ΔLi-sample

Development and test of Tritium Breeding Ratio (TBR) monitoring systems -Development of TBRMS for TBM -out-pile and laboratory systems for investigation of sample deliver to TBM, -methods and analysis systems for measurement of tritium breaded in the samples

Problem of TBR Precision Measurement Q reactor

Conception of TBR Monitoring