Current and Prospective Tests in Reactor MIR.M1 Alexey IZHUTOV - PowerPoint PPT Presentation

The 18th IGORR Conference 3-7 December 2017, The International Conference Centre, Darling Harbour, Sydney, Australia Current and Prospective Tests in Reactor MIR.M1 Alexey IZHUTOV

INTRODUCTION Research Reactor MIR.M1 – 50 years in operation Saint Petersburg Moscow Dimitrovgrad Ulyanovsk 90 km 160 km Samara – operating FA channel – experimental channel – combined operating FA with absorber – control rod channel 2 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

INTRODUCTION General Technical Data of the MIR.M1 Parameter Value Nominal thermal power , М W 100 Maximal thermal neutron flux density 5·10 14 in the loop channel , с m -2  s -1 230 ÷ 240 Power operation days per year, days Fuel UO 2 - 90% HEU Core height, mm 1000 The number of loop channels, pcs. 11 Planned life-time Till at least 2035 3 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

INTRODUCTION Parameters of MIR.M1 Loops Loops Parameter PV-1 PVK-1 PV-2 PVK-2 PVP-2 PG Water, Boiling Water Water, Water, Coolant Water Boiling, He, N 2 Boiling Steam Number of channels 2 2 2 2 1 1 Channel capacity, kW 1500 1500 1500 1500 2000 160 Coolant temp.,  С 350 350 350 355 550 600 Max pressure, MPa 16,8 16,8 17,8 17,8 20,0 20,0 Max flow rate , t/h 16,0 14,0 16,0 14,0 10,0 - 4 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS Preparation of experiments with fresh and fuel rods and spent fuel NPP 5 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS Irradiation rigs to test fuel and structural materials Channel vessel WWER-1000 full-size fuel rods Cable WWER-440 full-size fuel rods Shroud Reactor core Refabricated fuel rods Refabricated fuel rod instrumented Cladding with pressure transducer extensometer and thermocouple 6 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS Gauges for in-pile measurements installing installed in fuel rods 7 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS b) 12 Oxide film, µm 8 4 0 0 400 800 1200 FR bottom Length, mm FR top 9,16 Diameter, mm 9,12 9,08 9,04 0 400 800 1200 FR bottom FR top Length, mm *FR – fuel rod a) c) Design of interim inspection stand (a), design of ultrasonic cleaner (b), photo of interim inspection stand in the MIR.M1 storage pool (c) 8 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

KEY TRENDS IN FUEL TESTS Normal conditions, abnormal conditions (RAMP), maneuvering, design-basis accidents (LOCA, RIA) Testing complex of fuel and core components of nuclear reactors of different types Fission gas release from leaking fuel rods and Gd fuel Research reactor fuel rods with artificial defects 9 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

RAMP TESTS 1200 ○ - Tight VVER-1000 fuel rods Δ - Tight VVER-440 fuel rods ▲ - Leaking VVER-440 fuel rod 900 □ , ■ - Experimental fuel rods LHR, W/cm (tight and leaking ones, correspondingly) 600 300 0 0 10 20 30 40 50 60 70 Burnup, MWd/kgU a) b) Elongation gauges for a fuel Linear heat rate (LHR) vs of burnup rod (a) and fuel column (b) 3,0 3,0 R9 R11 LHR, rel. units LHR, rel. units 2,5 2,5 2,0 2,0 R1 R2 R3 1,5 1,5 R4 R5 R6 R7 R8 R12 1,0 1,0 0 50 100 150 200 0 10 20 30 40 Irradiation rig to test full- Time, m Time, h size and refabricated fuel Amplitude of LHR at RAMP tests (R 1… R12) rods under RAMP 10 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Testing under Power Cycling (Maneuvering) LHR ql max ql max ql min ql min n 1st CYCLES LHR ql max ql max ql min ql min Irradiation rig to test fuel rods under multiple power 1st n CYCLES cycling (maneuvering) Time Experiment scenario 1,0 1,0 Elongation, mm Elongation, mm 0,8 0,8 0,6 0,6 1 41 10 20 0,4 0,4 50 70 30 0,2 0,2 40 80 0,0 0,0 700 900 1100 1300 1500 700 900 1100 1300 1500 Temperature, °C Temperature, °C a) b) Relation between elongation of the VVER-1000 refabricated fuel rods (50 MWd/kgU) and fuel temperature under power maneuvering: first 40 cycles (a); other 40 cycles, and power ramping ( × ) after interim storage (b) 11 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

LOCA TESTS Temperature scenario in the experiment 900 ТС 1 Fuel cladding temperature, °C IV Shrou 800 d Basket V Insulato 700 r III 600 ТС 2 II Experiment 500 ТС 3 temperature 400 range I ТС 4 300 ТС 5 ts 200 Heater Up to 5 hours -300 -200 -100 0 100 200 300 400 500 600 Time, s 1000 ТС 6 Temperature, °C 800 Pressur e gauge 3 600 2 5 400 1 200 4 0 19:00 19:10 19:20 19:30 19:40 19:50 20:00 Time, h:m Change in the fuel cladding temperature a) b) (thermocouples 1, 2, 3) and coolant Irradiation rig to test a FA fragment (a) and single fuel rod (b) (thermocouples 4, 5) in the experiment 12 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

LOCA TESTS 840 7 1 760 6 2 Temperature, °C 4 Pressure, MPa 680 5 600 4 520 3 3 440 2 360 1 280 0 12:00 12:01 12:02 12:03 12:04 12:05 12:06 12:07 Time, hh:mm Rotation by 90 о Change in the fuel cladding temperature above the central (1), lower (2) and upper (3) spacer grids at 5…50 mm from the upper grid end. State of the fuel rod after MIR-LOCA/50 experiment (X-ray) Change in gas pressure (4). MIR-LOCA/50 experiment 13 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

RIA TESTS Pulse form in the MIR.M1 reactor 6 Heat rate, rel. units Time interval at constant power 5 4 3 2 1 TC data in the fuel column: 0 T1, T5 – refabricated 0 2 4 6 8 10 fuel rods 1,2; Time, s Т4 – non-irradiated fuel rod 1800 36 CMP Т4 Т5 1500 30 Temperature, о C ND data, mV 1200 24 Т5 Т1 900 18 Т1 Т4 600 12 300 ND data 6 0 0 Irradiation rig schematic 10 12 14 16 18 20 representation Time, s 14 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Fission Product Release Investigation of Leaking Fuel Rods N 2 PVP-1 1,00E+09 Activity, Bq/kg 1,00E+08 Change in the specific activity 1,00E+07 of inert radioactive gas 1,00E+06 Kr-85m Kr-87 in coolant during Kr-88 Kr-89 Xe-133 Xe-135 tests Xe-138 1,00E+05 0 3 6 9 12 15 18 21 24 On-line gamma Time, days spectrometer on 1,00E+09 the control I-131 I-132 I-133 I-134 Activity, Bq/kg 1,00E+08 I-135 1,00E+07 1,00E+06 1,00E+05 0 3 6 9 12 15 18 21 24 Time, days Change in the specific activity of iodine radionuclides in coolant during tests 15 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Activities to Enhance the MIR.M1 Reactor Safety After the Fukushima accident, all RIAR’s reactors were subject to analysis of consequences from all possible off-site impacts such as earthquake (6 grades), tornado and fire at the adjacent territory. Key tasks to enhance the MIR.M1 safety: 1. Long-term (for more than 24 hours) provision of power for safety-important systems. 2. Anti-seismic system implementation 3. Abgrading the fire protection system . 16

Emergency power supply system modernization New diesel-based emergency power supply system was put into operation 17

Anti-seismic system implementation Anti-seismic system was implemented able to control the reactor building and reactor supporting structure vibrations and output signals to the emergency system in case the set threshold is exceeded. Seismic sensor CMG-5TD- М. 18

Abrading the fire protection system New automatic fire detection and alarm system 19

Abrading the fire protection system 1. Nominal pump output, ls 10,0 2. Nominal pump pressure, m 60,0 3. Nominal rotation frequency, rot/min 3400 4. Nominal pumping head, m 1,5 5. Max pumping head, m 5,0 Installation of additional mobile water pumps 20

CONCLUSIONS MIR.M1 ’s Activities to further enlarge the experimental capabilities and develop promising areas of research:  improvement of the techniques to control parameters and perform in-reactor measurements of fuel rods characteristics;  reactor tests in justification of the improved and new types of VVER and PWR fuels under different designed conditions;  use of a gas-cooled loop to examine core components and FA dummies of high-temperature gas-cooled reactors;  reactor tests to improve and justify fuels of SMR;  permanently upgrading of the MIR.M1 reactor and its equipment and extension of its lifetime, including replacement of Be blocks. 21 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Thank you for your attention! For further information please contact: Alexey IZHUTOV JSC “SSC RIAR” Те l.: +7(84235) 3 20 21 Web: www.niiar.ru E-mail: adm@niiar.ru