Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions

Transcription

1 ROSATOM STATE ATOMIC ENERGY ОАО CORPORATION «ТВЭЛ» - российский ROSATOM производитель ядерного топлива Nuclear fuel for VVER-1200 Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions L.T. Yanko Executive Director, Business Development & Analysis, JSC TVEL April 2-3, 2012 Johannesburg, Sandton Convention Center

2 TVEL is producer and supplier of nuclear fuel Role of TVEL in Rosatom s Key Activities Fuel fabrication Mining TVEL Research and development Conversion and enrichment TVEL NPPs engineering & construction Power equipment and services Gas centrifuges manufacturing TVEL Spent nuclear fuel treatment Power Generation companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 2

3 Evolution of FA design parameters Parameter Design VVER-1000 VVER-1200 VVER-TOI FA type TVS-2M TVS-2006 TVS-TOI Mass of fuel in FA, kg Quantity of guide and instrumentation tubes, pcs Quantity of absorber rods in RCCA, pcs or 16 (for 15 RCCAs) Quantity of fuel rods in FA, pcs Fuel column height, mm Pellet dimensions, Dout / Dc.h 7,6х1,2 7,6х1,2 companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 3

4 340x10= x10= FA design and properties Resistance to shape deformation Ability of being disassembled Uranium content TVS- 2M TVS-2006 TVS-TOI Small vulnerability at fuel handling Processibility FA reliability (optimized pitch ( , SG quantity) TVS-2006 Location of instrumentation channel Independence of choice of coordinate for ICIS of RCCA position in the cell НК Bundle asymmetry, area of increased heat rate ИК Guide tube Instrumentation tube Fuel rod твэл companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 4

5 FA design and properties Component standardization Lower support shell Spacer grid FA top nozzle and collet assembly Bottom nozzle (from casting) Product (ADF not shown) Welded skeleton Billet companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 5

6 Heat transfer intensification Vortex Run Cell intensifiers of two types (devoid of spacing functions) are applied in FAs: turbulizing grid Vikhr ( Vortex ) (to increase the critical heat flux density) mixing grid Row-by-row run (to even the sectional enthalpy).they are located in four 340 mm upper spans. companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 6

7 Fuel cycle parameters FA type Fuel cycle 4х1 5х1 3х1,5 FA for AES-2006 TVS-2M blanketfree FA for AES-2006 (RRC KI Report No. 32/ ) TVS-2M blanket-free FA for AES-2006 (RRC KI Report No. 32/ ) Qnty of make-up fuel, pcs Average FA enrichment, % 4,79 4,83 4,83 4,89 4,69 Length of fuel residence time, eff. days (without power effect) Burnup in the unloaded FAs, MWD/kg U - average ~ , , ,8 58,5 58,4 51,9 48,4 - maximum 59,7 67,2 64,2 60,3 56,4 Specific consumption of natural uranium, kg/mw eff.days 0,199 0,187 0,191 0,214 0,240 companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 7

8 Licensing challenges for high burn-up fuel Design values of VVER fuel burn-up Project Document Fuel cycle AES-2006 Project PSAR Technical designs of fuel rods and core 4х1 5х1 Maximum burnup, MW*day/kgU Value Across FA ~60 Across fuel rod 66 Across pellet 72 Across FA ~64 Across fuel rod 77 Across pellet 83 companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 8

9 Basis for licensing General operability Shape deformation. Gas release, corrosion deposits) Achieved burnup - TVS-2(2M) (51,84 MW*day/kgU) -TVSA (66,05 MW*day/kgU) FA post-irradiation tests (50 MW*D/kgU) Fuel rod post-irradiation tests (73 MW*D/kgU) LOCA (Justification of MDBA) In MIR.M1 reactor (~60 & ~70 MW*D/kgU) RIA In BIGR reactor (~60 MW*D/kgU) In MIR.M1 reactor (78, 59 and 67 MW*D/kgU) Transients, including load follow operation* RAMP 150 (W/cm 360)W/cm with burnup ~70 MW*D/kgU 300 cycles ( )% with burnup 52 MW*D/kgU *(in MIR.M1 reactor) MW*D/kgU companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 9

10 VVER-1200 Nuclear Fuel design Development trends FA basic design Tp= 3200 MWt Campaign eff. days Enrichment up to 4.95% Pellet 7.6/1.2 mm, Core height 3730 mm UO 2 mass 534 kg Burn up 64 MWt days/kg U Daily maneuvering % N Fuel supply - 22 FA design development Tp= 3300 MWt Enrichment up to 4.95% Pellet 7.8/0мм Core height 3730 мм UO 2 mass 580 кг Heat exchange intensifiers Daily maneuvering % FA design correction 2015 Improvement of calculation codes: Development of codes linked with thermal hydraulic and neutron and physical core calculations; DNB calculation methodology improvement per local parameters; Best assessment methodologies and codes application; Using of statistical methods during calculation of DNBR. Increase of enrichment up to more than 5% Enrichment up to 7% UEr fuel Zr alloys E110М, E635М & E125 Substantiation and development of FA design year cycle (Campaign 680 eff. days ) Number of feed FA 20% less Average burn up rise % Lower fuel component 6-9 % companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 10

11 Proposals for improvement Increase in uranium content Enrichment, % 4,95 Fuel pellet diameters, mm 7,6/1,2 Fuel column height, mm ,5 FA Мах 600days < 2 annual cycles Enrichment, % 4,95 Fuel pellet diameters, mm 7,8/0 Fuel column height, mm ,5 FA 645 days 2 annual cycles Pro Meeting the Customers needs Availability of operating experience The same diagram of pellet-to-cladding interaction> 40kW s/kg U Contra Absence of justified criteria Absence of operational background companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 11

12 Proposals for improvement. Increase in initial enrichment and replacement of Gd with Er Fuel cycle 12 mnth (4х1) Quantity of make-up fuel rods, pcs. UO2 18 mnth (3х1,5) 24 mnth Gadolinium Erbiu m Erbium /84 FA average enrichment,% 4,79 4,762 5,523 5,720 6,340/6,320 Length of fuel loading operation, eff.days (without power effect) Burnup in the unloaded FAs, MWD/kg U average maximum , /647 55,8 59,7 47,5 52,3 59,3 69,5 59,3 68,3 58,5 68,1 Specific consumption of natural uranium, kg/mw eff.days 0,199 0,227 0,213 0,221 0,249/0,248 companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 12

13 FA transportation The packages are allowed for transportation only if the approval certificate confirming the compliance of the Transport Package (PCS) design with the requirements of IAEA «Safety Regulations for Radioactive Material Transportation» TS-R-1 is available; Quantity of FA loaded into a PCS - 2 Service life PCS - year 20 companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 13

14 Delivery modes Transportation Legal basis NPP operatot NPP operator NPP operator NPP operator NPP operator By air By railroad By sea Intergovernmental agreement Long-term contract Transport packing sets (TPS) Suitable for transportation by all transport means; The only TPSs in the World that pass full scale tests (incl. 90 m/s acceleration); Equipped with shock sensors. companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 14

15 Thank You for Attention! Address: 49 Kashirskoe chose, Moscow , Russia Tel.: Fax: