Current and Prospective Tests in Reactor MIR.M1

Transcription

1 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

2 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

3 INTRODUCTION General Technical Data of the MIR.M1 Parameter Value Nominal thermal power, МW 100 Maximal thermal neutron flux density in the loop channel, сm -2 s 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

4 INTRODUCTION Parameters of MIR.M1 Loops Coolant Parameter Loops PV-1 PVK-1 PV-2 PVK-2 PVP-2 PG Water Water, Boiling Water Water, Boiling Water, Boiling, Steam He, N 2 Number of channels Channel capacity, kw Coolant temp., С 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

5 EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS Preparation of experiments with fresh and fuel rods and spent fuel NPP 5

6 Reactor core 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 Refabricated fuel rods Refabricated fuel rod instrumented with pressure transducer and thermocouple Cladding extensometer 6

7 EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS Gauges for in-pile measurements installing installed in fuel rods 7

8 EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS b) Oxide film, µm FR bottom Length, mm 1200 FR top 9,16 Diameter, mm 9,12 9,08 9,04 0 FR bottom Length, mm 1200 FR top a) c) *FR fuel rod Design of interim inspection stand (a), design of ultrasonic cleaner (b) photo of interim inspection stand in the MIR.M1 storage pool (c) 8

9 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 rods with artificial defects Research reactor fuel 9

10 RAMP TESTS LHR, W/cm Tight VVER-1000 fuel rods Δ - Tight VVER-440 fuel rods - Leaking VVER-440 fuel rod, - Experimental fuel rods (tight and leaking ones, correspondingly) Irradiation rig to test fullsize and refabricated fuel rods under RAMP a) b) Elongation gauges for a fuel rod (a) and fuel column (b) LHR, rel. units 3,0 2,5 2,0 1,5 1, Burnup, MWd/kgU Time, m Linear heat rate (LHR) vs of burnup R1 R2 R3 R4 R5 R6 R7 R8 R12 Amplitude of LHR at RAMP tests (R1 R12) LHR, rel. units 3,0 2,5 2,0 1,5 1,0 R9 R Time, h 10

11 Testing under Power Cycling (Maneuvering) LHR ql max ql max ql min ql min 1st CYCLES n LHR ql max ql max ql min 1,0 ql min Experiment scenario 1st CYCLES n Time 1,0 Irradiation rig to test fuel rods under multiple power cycling (maneuvering) Elongation, mm 0,8 0,6 0,4 0,2 0, Temperature, C Elongation, mm 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) 0,8 0,6 0,4 0,2 0, Temperature, C 11

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

13 LOCA TESTS Temperature, C Pressure, MPa :00 12:01 12:02 12:03 12:04 12:05 12:06 12:07 Time, hh:mm 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. Change in gas pressure (4). MIR-LOCA/50 experiment 0 Rotation by 90 о State of the fuel rod after MIR-LOCA/50 experiment (X-ray) 13

14 RIA TESTS CMP Heat rate, rel. units Pulse form in the MIR.M1 reactor Time interval at constant power Time, s Temperature, о C Т4 Т1 Т5 TC data in the fuel column: T1, T5 refabricated fuel rods 1,2; Т4 non-irradiated fuel rod 36 ND data Т4 Т5 Т ND data, mv Irradiation rig schematic representation Time, s 0 14

15 Fission Product Release Investigation of Leaking Fuel Rods N 2 PVP-1 1,00E+09 Change in the specific activity of inert radioactive gas in coolant during tests Activity, Bq/kg 1,00E+08 1,00E+07 1,00E+06 1,00E+05 Kr-85m Kr-88 Xe-133 Xe-138 Kr-87 Kr-89 Xe Time, days ,00E+09 I-131 I-132 1,00E+08 I-133 I-134 I-135 Activity, Bq/kg 1,00E+07 1,00E+06 On-line gamma spectrometer on the control 1,00E Time, days Change in the specific activity of iodine radionuclides in coolant during tests 15

16 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

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

18 Anti-seismic system implementation Seismic sensor CMG-5TD-М. 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. 18

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

20 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 Nominal pumping head, m 1,5 5. Max pumping head, m 5,0 Installation of additional mobile water pumps 20

21 CONCLUSIONS Activities to further enlarge the MIR.M1 s 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

22 Thank you for your attention! For further information please contact: Alexey IZHUTOV JSC SSC RIAR Теl.: +7(84235) Web: adm@niiar.ru