LVR-15 Reactor Application for Material Testing. Nuclear Research Institute Řež,, plc Reactor Services Division

Transcription

1 LVR-15 Reactor Application for Material Testing M. Marek,, J.Kysela Kysela,, J.Burian Nuclear Research Institute Řež,, plc Reactor Services Division

2 Research Reactor LVR-15 Light-water moderated and cooled tank nuclear reactor with forced cooling. Maximum thermal power of 10 MW The fuel type IRT-2M enriched to 36% Combined water-beryllium reflector 5 kg of 235U 28 to 31 fuel elements

3 LVR-15 cross section

4 LVR-15 - Core cross section

5 The LVR-15 reactor horizontal cross section

6 Reactor Characteristics maximum reactor power maximum thermal neutron flux in the core maximum fast neutron flux in the core thermal neutron flux at the end of the horizontal beam tube thermal neutron flux in irradiation channel in fuel thermal neutron flux in irradiation channel in reflector 10 MWM 1.5x n/m 2 s 3x10 18 n/m 2 s 1x n/m 2 s 1.2x n/m 2 s 9x10 17 n/m 2 s

7 Fuel Element total length active length section square mass of the assembly 882 mm 580 mm 71,5 x 71,5 mm 3,2 kg

8 Fuel Element (cont.) tube wall thickness cladding thickness fuel material mass of 235 U 235 U enrichment 2 mm min.0,4 mm UO 2 Al 230 g 36%

9 The Reactor Serves as a Radiation Source for: Material testing experiments in water loops and irradiation rigs Activation analysis with the pneumatic rabbit system Experiments at beam tubes in the field of nuclear and applied physics Irradiation of iridium for medical purposes Irradiation for radio-pharmaceuticals production Irradiation of silicon mono crystals Neutron capture therapy project

10 Reactor Dosimetry According to the type of experiment different demands on reactor dosimetry are expected. Neutron spectra, thermal and fast neutron flux densities and their changes during the irradiation, final neutron fluences,, gamma radiation heating and absorbed doses are to be measured. To fulfil these demands, several measures are taken: irradiation position assessment instrumentation design mock up experiment radiation monitoring post-irradiation evaluation

11 Reactor Dosimetry (cont.) Irradiation position assessment The power and neutron group flux densities distribution in the core - NODER 4 groups diffusion code. The macroscopic constants - the use of WIMSD4 and WIMSD4-M M codes. Fast neutron and gamma ray spectra calculation DORT transport with the BUGLE-96 coupled cross section library of 47 neutron and 20 gamma groups. Monte Carlo neutron and particles transport code MCNP 4A with the ENDF/B-VI cross-section section library

12 Reactor Dosimetry (cont.) Neutron dosimetry Activation monitors thermal, resonance, threshold, fission Neutron spectrum measurement Neutron flux distribution Foils, wires. Adjustment procedure - calculated spectra combined with activation monitors determination of neutron flux densities, fluences,, and integral values Self-powered neutron detectors (SPNDs( SPNDs) Neutron flux prediction in irradiation position Neutron flux densities distribution along the reactor core height.

13 Reactor Dosimetry (cont.) Gamma heating Reactor calorimeter or string of calorimeters can be used for the gamma radiation heating measurement and monitoring. Type 1 - inside the reactor core (ŠKODA Nuclear Machinery Ltd.) Type 2 - at the reactor core periphery.

14 Experimental Facilities High-pressure water loops Vertical channels for material testing (rigs) Vertical irradiation channels Pneumatic rabbit system for short-time time irradiation Nine horizontal channels (beam tubes) BNCT facility Hot cells

15 RVS 3 Loop The loop is designed for material and radioactivity transport investigation under PWR/VVER conditions. The RVS-3 3 loop facility enables to perform irradiation experiments in wide range of operational parameters limited by following maximum parameters : Pressure 16.5 MPa Temperature 345 C Water flow rate kg/hr Neutron flux ~1x10 18 n/m 2 s Electrical heating capacity 100 kw

16 RVS 3 Loop Diagram

17 RVS 3 Loop Irradiation Channel

18 RVS 3 Loop Investigation of structural materials mechanical properties degradation and corrosion behaviour under irradiation and PWR/VVER water chemistry and thermal- hydraulic conditions Investigation of behaviour (corrosion, hydriding) ) of fuel cladding materials under influence of irradiation, thermal flux and water chemistry conditions

19 RVS 3 Loop Investigation of radioactivity transport and behaviour under PWR/VVER conditions (e.g. Influence of water chemistry, pht regime, zinc injection ammonia, etc.) Testing of high-temperature, high pressure sensors for water chemistry monitoring.

20 BWR 1 Loop The loop is designed for investigation of structural materials behaviour and radioactivity transport under BWR conditions. The BWR-1 1 loop facility enables to perform irradiation experiments in wide range of operational parameters limited by the following maximum parameters: Pressure 10 MPa Temperature 300 C Water flow rate kg/hr Neutron flux ~1x10 18 n/m 2 s

21 BWR 1 Loop Diagram

22 BWR 1 Loop Investigation of materials mechanical properties degradation and corrosion behaviour under irradiation and BWR water chemistry conditions. Investigation of radioactivity transport and behaviour under BWR conditions (e.g. Hydrogen water chemistry, zinc injection, etc.). Testing of high-temperature, high pressure sensors for water chemistry monitoring.

23 BWR 2 Loop The experimental water loop shall be used for the material research of BWR reactors under conditions simulating the operation of BWR reactors (pressure, temperature, radiation, fluid analysis). Pressure 12 MPa. Temperature 300 C. Water flow rate kg/hr. Force applied to the specimen 150 kn.

24 BWR 2 Loop Diagram

25 BWR 2 Loop Irradiation Channel IASCC of RPV and core internals 2CT & 1CT specimens, hydraulic loading cycling/constant load MPa m, ferritic & austenitic steels, BM, HAZ

26 HTR Materials Irradiation - He Loop conceptual design Material performance in He at high temperature and under the influence of impurities such as H 2 O, CO 2 Temperature ºC Flow rate 20g/s He pressure of 7 Mpa Purification system

27 SCWR Materials Irradiation Loop conceptual design Objectives: Materials performance under the combined influence of supercritical water and irradiation Temperature 600 C Pressure of 25 Mpa

28 Irradiation Rigs Cylindrical, flat Full temperature control Four types of specimens: Tensile specimen CT specimen Round CT specimen Charpy-v v specimen

29 CHOUCA Irradiation Rig Independent and controlled heating in sections Thermocouples Neutron monitoring

30 Flat Irradiation Rig Independent and controlled heating in sections Thermocouples Neutron monitoring

31 Flat Irradiation Rig Rig cross-section section 70 x 70 mm x 70 mm 2 Sample cross-section section 60 x 60 mm x 60 mm 2

32 Experimental Base for GIV Reactor Systems Experience based on long term research in material, water chemistry and radiolysis tests for PWR, VVER and BWR The experience for SCWR is based on water chemistry and materials studies going from PWR (VVER) to BWR reactor irradiation condition The experience for HTR/VHTR is based on material irradiation for ADTT and big samples (CCT) irradiation of RPV

33 Experimental Projects Material degradation studies (SCC): IASCC of RPV and core internals (for VGB) 2CT & 1CT specimens, hydraulic loading cycling/constant load MPa m, ferritic & austenitic steels, BM, HAZ, BWR environment, ECP monitoring; preirradiation in inert gas at flat rig In-pile and out-of-pile SSRT studies (for EPRI) pre-irradiated tensile specimens ( 2 mm), 10 dpa, hydraulic loading, deformation rate 10-6 /10-7 s -1, PWR environment Irradiation of RPV steels (for JAPEIC) dry irradiation, weldments SSRT of pre-irradiated austenitic specimens, up to 20 dpa (for CEZ)

34 Experimental Projects Zr-alloys cladding corrosion (electrically heated fuel rod imitators): Zr-alloys behaviour at PWRs conditions (for FRAMATOME) new alloys (incl. M4, M5),, PWR chemistry, high Li, subcooled boiling, corrosion, hydriding Zr-4 4 and Zr-1% 1%Nb behaviour at VVERs conditions (for SONS, IAEA support) compatibility study, corrosion, hydriding,, K/NH 3 chemistry Russian Zr-alloys (E110, E635) corrosion behaviour in PWR conditions subcooled boiling, corrosion, hydriding

35 Experimental Projects Water chemistry influence on radioactivity transport and build-up: up: Effect of Zinc injection in PWR conditions on corrosion and radioactivity build-up up (for NUPEC/MHI) Ammonia/Hydrogen/Zinc addition chemistry effect on radioactivity build-up up in VVER conditions (for CEZ, SE); comparison studies, radioactivity transport, radiochemistry modelling Optimisation of VVER primary water chemistry; standard ph, high ph (7.4) and hydrazine chemistry, corrosion & corrosion products release, radioactivity build-up up Development and testing of a primary surface pre-conditioning technology HTCT (Hydro-thermal Chromium Treatment) Investigation of high-temperature electromagnetic filtration

36 Experimental Projects High-temperature sensors testing Irradiation of a potential structure materials for ECP sensors (for( ANERI/Hitachi/Toshiba); BWR environment ECP sensors testing under irradiation (for ANERI/Hitachi); BWR environment, different types of ECP sensors, water chemistry changes (NWC/HWC), life-time Fusion programme (EFDA) Corrosion behaviour and mechanical properties of fusion reactor structure materials (e.g. EUROFER) under fusion blanket or primary ry first wall relevant conditions (e.g. liquid metal Pb-17Li, neutron irradiation, thermal cycling, hydrogen embitterment) ADTT programme Potential structure materials corrosion behaviour and compatibility ity with molten salts (fluoride-based molten salts) Verification of neutron-physics calculations

37 Fusion Reactor Structural Materials In-pile Rig for Corrosion Tests in Pb-Li Eutectic Alloy Fusion Reactor (ITER); structural material (EUROFER) EUROFER material specimens in the irradiation capsule filled with Pb-15.8Li Test temperature (approx. 500 C) and temperature gradient (~ C) in the capsule Flow of the molten Pb-Li eutectic is driven by natural convection (in the range of few mm/s). Computer code COSMOSFloWorks has been used to define and verify design of the experimental capsule (e.g. capsule dimensions, cooler design, number of specimens etc.). Calculation results indicate good agreement between measured and required temperatures.

38 Fusion Reactor Structural Materials Principle Design of the Pb-Li In-pile Rig

39 Fusion Reactor Structural Materials Pb-Li In-pile Rig Tcal=530 0 C Tmeas=526,9 0 C Comparison of Calculated and Measured Temperatures COSMOSFloWork calc. Tcal=390 0 C Tmeas=420 0 C

40 Primary ITER First Wall Mock-up CuCrZr Beryllium

41 Neutron Transmutation Doped Silicon Maximum crystal dimensions: Diameter 3 3 (4 ) Length 20 cm (30 cm) Typical parameters of irradiation channel (10 MW): Thermal neutron flux: 2 x n/m 2 s Fast neutron flux: 2 x n/m 2 s

42 Radionuclides Production Unsealed sources for nuclear medicine diagnostic and therapy Sealed sources for the radiation oncology Sealed sources for commercial irradiation

43 Activation In Reactor Radio nuclides for radio pharmacy 153 Sm, 161 Tb, 165 Dy, 166 Hop, 169 Er Radio nuclides for generator systems 99Mo- 99m Tc, 113 Sn- 113m In, 188 W- 188 Re 99 Mo 99m Tc, 113 Sn 113m In, 188 Re Radio nuclides for sealed technical and medicinal sources: e.g. 60 Co, 192 Ir, 182 Ta, 198 Au

44 Irradiation Possibilities Rotary irradiation channels DONA φ 63,5 and φ 80 mm Max. neutron flux density: 2 x n/m 2 s Narrow channel in Be reflector -φ 40 mm Max. neutron flux density: 9 x n/m 2 s Wide channel in H 2 O reflector -φ 62 mm Max. neutron flux density: 9 x n/m 2 s Wide channel surrounded with fuel -φ 62 mm Max. neutron flux density: 1.4 x n/m 2 s

45 Irradiation Capsule for 192 Ir Wire Sources

46 Boron Neutron Capture Therapy Treatment of human brain gliomas Clinical tests of the therapy Phase I study toxicity of the BNCT 9 patients in the project 5 patients treated

47 BNCT Beam Design

48 BNCT Beam Parameters Φ th = (1.12 ± 0.05)x10 8 cm -2 s -1 Φ epi = (6.98 ± 0.27)x10 8 cm -2 s -1 Φ fast = (6.94 ± 0.40)x10 7 cm -2 s -1 (dk fn /dt)/φ epi =1.45x10-12 Gy cm 2 (estimated 20%) (dk g /dt)/φ epi =7.88x10-13 Gy cm 2 (estimated 20%)