The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus

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1 The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus on behalf of YALINA team Dr. Kiyavitskaya H. ISTC meeting «Feature technology: cooperation Spain and Republics of SIG»,? adrid, April 2010

2 Content Introduction YALINA zero power model of ADS ISTC Projects? B-070? B1341 IP EUROTRANS ISTC Project B1732 Conclusion

3 Subcritical facility YALINA ion accelerator, 2 target unit, 3 subcritical assembly, 4 measuring complex

4 The ISTC Project #B-070 Ion accelerator - or DT-targets: 230 or 45 mm

5 Main parameters of the neutron generator NG-12-1 Accelerator H+ and D+ Beam energy, kev Beam current, ma Pulse duration, s ( ) 10-6 Pulse repetition frequency, Hz ( ) Spot size, cm ?i 3 H target, mm Rotation speed, rpm Maximal yield of neutrons, n/s ( )x x10 11 Neutron energy, MeV 13-15?iD target, mm Maximal yield of neutrons, n/s (2 3)x10 10 (2-3)x10 9 Neutron energy, MeV 2.5 3

6 YALINA facility: YALINA-Th and YALINA-Booster 6x10 8 Neutron fluence (cm -2 s -1 ) 5x10 8 4x10 8 3x10 8 2x10 8 1x10 8 R (cm) 5 cm 10 cm 16 cm Neutron energy (ev) EC2B F(E) Cf DD DT Energy, (MeV)

7 YALINA facility allows to study Neutronics and kinetics of ADS Neutronics of fast and thermal reactors International benchmarks?the IAEA Coordinated Research Projects (CRP) Analytical and Experimental Analysis of Accelerator Driven Systems and Low Enriched Uranium Fuel Utilization in Accelerator Driven Sub-Critical Assembly Systems

8 Subcritical facility VENUS (China)

9 Subcritical facility GUINEVERE Neutron gener ntrol rooms

10 International Projects at YALINA facility ISTC Project B-70 ( ),?? (??H, FzK, CIEMAT)? «Experimental and theoretical investigations of the peculiarities of transmutation of long-lived fission products and minor actinides in the subcritical assembly driven by a neutron generator» IP EUROTRANS:? Domain 2, task 2.1 YALINA-experiment ISTC Project?-1341 ( ), USA (?NL)? «Analytical and experimental evaluating the possibility of creation of universal volume source of neutrons in the sub-critical booster assembly with low enrichment uranium fuel driven by a neutron generator» ISTC Project B1732 ( ) USA (?NL)? «Analytical and experimental evaluating the possibility of creation of universal volume source of neutrons in the sub-critical booster assembly with low enriched uranium fuel driven by the neutron generator»

11 International collaboration at YALINA-facility (Spain, Sweden, USA, Russia, Belarus, France, Belgium, Germany, Czech Republic) #B-070 Project: Foreign Collaborators Royal Institute of Technology,Stockholm, Sweden Institute of Nuclear Physics,Karlsruhe, Germany CIEMAT, Madrid, Spain #B1341 and B1732 Projects: Foreign Collaborator Argonne National laboratory, USA

12 #B-070 Project: assembly (1) YALINA-Thermal MC1 MC2 EC2 EC3 EC5 EC4 EC1 EC7 EC6 MC3 MC4 Polyethylene Lead Graphite Fuel pins EK-10 Holes in polyethylene Neutron flux monitoring channels MC1- MC4 Experimental channels in the core EC1-EC4 Experimental channels in reflector EC5-EC7

13 Experimental program YALINA (2) Subcriticality level measurements?source multiplication method?pns-method Sjöstrand method (area method) Gozani method Unfolding of neutron spectra based on the threshold reaction rates Transmutation reaction rates for I, Am, Np

14 YALINA-Thermal assembly (3) 1,E-02 dn/de, neutron/(s*cm^2) 1,E-03 1,E-04 1,E-05 1,E-06 1,E-07 1,E-08 MCNP calculation Unfolding 1,E-09 0,0 5,0 10,0 15,0 20,0 E, MeV Reaction rate (normalized per one neutron and one nuclei), c -1 n -1 0,55 Np-237, R = 10 cm 0,50 0,45 0,40 0,35 0,30 0,25 experiment calculation Reaction rate (normalized per one neutron and one nuclei), c -1 *n -1 0,85 0,80 0,75 0,70 0,65 0,60 0,55 0,50 0,45 0,40 0,35 0,30 0,25 0,20 0,15 I-129, R=5 cm calculation experiment

15 YALINA-Pb assembly (4) MC1 MC2 EC2 EC3 EC5 EC4 EC1 EC7 EC6 MC3 MC4 Polyethylene Lead Graphite Fuel pins EK-10 Holes in polyethylene Neutron flux monitoring channels MC1- MC4 Experimental channels in the core EC1-EC4 Experimental channels in reflector EC5-EC7

16 IP-EUROTRANS (1) European research programme for the transmutation of high level nuclear waste in an accelerator-driven system (6th EC framework programme)? Domain 2: To test and validate possible methods for online monitoring of reactivity in subcritical systems.? Task 2.1: YALINA-Booster Reactivity measurements in a coupled fast-thermal heterogeneous system driven by pulsed or continuous neutron source. YALINA-Booster is the only installation where the reactivity monitoring techniques used in a power ADS can be tested

17 IP EUROTRANS (2) 5 configurations of the core (request of the partners) Subcriticality level measurements?pns method Area method (Sjöstrand method) a-feynman method? Beam trip experiments?current-to-flux experiments?neutron noise experiments

18 The ISTC Project?-1341 (1) The main subject is analytical and experimental evaluating the possibility of creation of universal volume source of neutrons in the sub-critical booster assembly with low enrichment uranium fuel driven by a neutron generator The subjects of B-1341:? Conversion of HEU (90 and 36% enrichment) to LEU YALINA-B without penalty of its neutronics? Development and testing of the experimental methods for subcriticality level monitoring? Unfolding of neutron spectra? Measurements of transmutation reaction rates for LLFP and MA

19 #B1341 Project (2) Experimental measurements in a zero (without nuclear fuel) YALINA assembly with 252 Cf, D,D and D,T neutron sources Fuel load and start-up of the HEU fuel YALINA-Booster. Measurements of sub-criticality levels by different experimental techniques, estimation the reactivity worth of the assembly replaceable elements etc.).

20 #B1341 Project (3) Experimental measurements in HEU YALINA-Booster with 252 Cf, D,D and D,T neutron sources (spatial distribution of neutron flux density, time dependence of neutron flux density by different ion pulse durations, neutron spectra by solid state track detector technique and by activation method of threshold reaction rates). Unfolding neutron spectrum by threshold reaction.

21 Main configurations of the YALINA-Booster core (4) Four main core configurations of the YALINA-Booster assembly are under consideration: 1st and 2nd configuration - HEU fuel YALINA-Booster - with 132 fuel rods with U m of 90% enrichment by 235 U in the inner part of fast zone; 563 fuel rods with UO 2 of 36% enrichment by 235 U in the outer part of fast zone, 902 and 1141 fuel rods (EK-10) with UO 2 of 10% enrichment by 235 U in thermal zone. 3rd configuration - LEU fuel YALINA-Booster (1st step) -with 695 fuel rods with UO 2 of 36% enrichment by 235 U in fast zone and 1185 fuel rods (EK-10) with UO 2 of 10% enrichment by 235 U in thermal zone. 4th configuration - LEU fuel YALINA-Booster (2nd step) with 601 fuel rods with UO 2 of 21% enrichment by 235 U in fast zone and 1185 fuel rods (EK-10) with UO 2 of 10% enrichment by 235 U in thermal zone.

22 Cd ration along experimental channels EC1B, EC2B Comparioson YALINA-Booster 90% and 36% (5) Cd ratio 2,8 2,7 2,6 2,5 2,4 2,3 2,2 2,1 2,0 1,9 1,8 1,7 1,6 1,5 1,4 1,3 1,2 1,1 1,0 Small size 3 He detector, 252 Cf source 90% (132)+36% (563)+10% (1141), EC1B channel 36% (695)+10% (1185), EC1B channel 90% (132)+36% (563)+10% (1141), EC2B channel 36% (695)+10% (1185), EC2B channel Z, cm

23 #B1732 Project (1) D E F G H I 4 5 EC1B 6 EC2B 7 8 EC4B EC3B 9 Ionguide Problem fuel channels (18) Valve zone, 108 rods with Umet. (nat.) Valve zone, 116 rods with B4C Fuel rods with UO 2, 21% enrichment by U-235 (601) Empty fuel channels (76) EC1B-EC3B - experimental channels in fast zone EC4B - experimental channel in fast zone

24 Distribution of small size 3 He detector counting rate along the experimental channels of fast (a) and thermal zone (b) by 252 Cf neutron source at Z=0 (2) N, 1/s EC3B EC2B EC1B He3_small+INK %_ % N, 1/s EC5T EC7T EC6T He3_small, INK % % Z [mm] Z [mm] Counting rate of 3 He detector Cf in Z=0 36% (695)+10% (1185) 21% (601)+10% (1185) EC3B channel Counting rate of 3 He detector, s EC6T channel Cf in Z=0 21% (601) + 10% (1185) 36% (695) + 10% (1185)

25 Conclusion It was shown that ion accelerators can be used to study neutronics and kinetics of ADS Two subcritical assemblies were designed, build and put into operation. Received experimental data are used to R&D of ADS projects (SAD, RACE, MYRRHA, EFIT, GUINEVERE and etc.)

26 Conclusion (cont.) YALINA-Booster experiments performed during the conversion of the inner part of the fast zone to use nuclear fuel with reduced uranium enrichment reached the following conclusions:?the experimental results obtained by the use of PNS area method become more correct as the effective multiplication factor exceeds 0.8.?The delayed neutron fraction value is used based on calculations but it needs experimental verification.

27 Conclusion (cont.) The discrepancy between the experimental (PNS method) and calculated effective multiplication factor is less than 0.5%. The kinetic parameters (neutron generation time, effective fraction of delayed neutrons, etc.) are defined by the thermal zone.

28 Conclusion (cont.) Replacement of the 90% enriched metallic uranium fuel in the inner part of the fast zone by 36 % enriched uranium dioxide fuel reduced the contribution of fast zone to the total reactivity of the assembly, resulted in softening neutron spectrum in the inner part of fast zone. The neutron spectrum of the thermal zone remains unchanged.

29 Thank you!