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NSC KIPT Nuclear Energetic Activity Ivan Nekliudov Ivan Karnaukhov

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NSC KIPT Nuclear Energetic Activity Ivan Nekliudov Ivan Karnaukhov NSC KIPT Nuclear Energetic Activity Ivan Nekliudov Ivan Karnaukhov [email protected] National Scientific Center Kharkov Institute of Physics&Tecnology Kharkov Ukraine Madrid April 21-24 2010 CONTENTS 1. Safe Fast Reactor Based on Self-Sustained Regime of Nuclear Burning Wave 2. Design and Analyses of KIPT Electron Accelerator Driven Subcritical Assembly Facility Concept 3. DIAGNOSTIC INSPECTION OF STRESS-DEFORMATION CONDIONS OF VVER-1000 REACTORS VESSEL 4. Behavior of core region of a reactor VVER-1000 ??? at heavy accident 5. Quasi-Monochromatic Compton X ray source 6. Technology on radioactive waste (RAW) isolation 7. Solid phase joining of heterogeneous materials of the type (Stainless steel- C22E, S. Steel - Zr) – the way of life extension of NPS equipment 8. Nuclear methods for analysis of nuclear fuel cycle materials and environmental objects 9. Why accelerators are necessary? 10. System of dosimetry control in NSC KIPT 1. Safe Fast Reactor Based on Self-Sustained Regime of Nuclear Burning Wave Lev Feoktistov (USSR, 1988): Nuclear Burning Wave L.P. Feoktistov. Preprint IAE-4605/4, 1988. Nuclear Extinction Burning Breeding Fertile ashes L.P. Feoktistov. Sov. Phys. Doklady, 34 (1989) 1071. zone zone zone zone zone Concept & Analytical approach Feoktistov 238U (n,g) ® 239U (b) ® 239Np (b) ® 239Pu (n,fission) ... PuPu NNeq> cr criterion T1/2 » 2.35 days Edward Teller (USA, 1997): Traveling Wave Reactor Monte Carlo simulation 232Th (n,g) ® 233Th (b) ® 233Pa (b) ® 233U (n,fission) ... E.Teller. Preprint UCRL-JC-129547, LLNL,1997. T1/2 » 27 days Hiroshi Sekimoto (Japan, 2001): CANDLE Deterministic approach U-Pu fuel cycle, Stationary problem: x = z + Vt H.Sekimoto et al., Nucl. Sci. Eng., 139 (2001) 306. Non-Stationary Theory of Nuclear Burning Wave S. Fomin, A. Fomin, Yu. Mel’nik, V. Pilipenko, N. Shul’ga (NSC KIPT, Kharkov, Ukraine) r R 238 U 238 U 100 % 90 % j ext 239 Pu L L z 10 % ign Ignition zone Breeding zone Nuclear Burning Wave Non-Stationary Non-Linear Multi-Group Diffusion Equation of Neutron Transport ggg 11¶F¶g¶F¶g¶F gggg®gggg--11 g -rDD-+(Sa+Sin+Smod-Sin)F-SmodF= v¶tr¶r¶¶¶rzz GG g -1 gg/g/jjg/g/jjjggg//® =cfå(nfSf)F-ååjcdlblå()nfSflF+åjlcldåålCl+SFin g/=1gg//==11 Together with Fuel Burn-up Equations and Equations of Nuclear Kinetics ¶N l æggggöæö ¶N =-ssF+LNN+F+L 9 çååall÷lç÷c(l-1)(ll--1)(1) ,(lN=1¸8);;=L66 ¶t èggøèø ¶t of Precursor Nuclei of Delayed Neutrons ¶N10 æög g j =Fååç÷s fllN ¶Cl jjjggg ¶t lg=1,4,5,6,7 èø =-llCl+bnlå()fSFfl ¶t g Nuclear Burning Wave in Fast Reactor with U-Pu Fuel Reactor radius R=117cm, Reactor composition (volume fractions): Fuel (238U) = 44%, Coolant (Pb-Bi) = 36%, Constr.material (Fe) = 20% Neutron Flux F (r, z, t) & Plutonium Concentration NPu (r, z, t) , 1017 c? -2 s-1 , 1021 c? -3 Fuel Burn-up for U-Pu Cycle Fission products Pu 238U Main features of NBW reactor with mixed Th-U-Pu fuel cycle Example: Metallic fuel 232Th (62%) + 238U (48%) volume fraction = 55%, fuel porosity p = 0.65; Coolant (Pb-Bi eutectic) vol. frac. = 30%, Constr. materials (Fe) vol. frac. = 15%; R = 390 cm - long-term (decades) operation without refueling and external control - negative feedback on reactivity - inherent safety - possibility of 232Th and 238U utilization as a fuel - fuel burn-up depth for both 238U and 232Th ˜ 50% - possibility of nuclear waste burn out (expected) - neutron flux in active zone ˜ 3·1015 n/?m2s - energy production density in active zone ˜ 200 W/?m3 - total power at the steady-state regime ˜ 5 GW - wave velocity at the steady-state regime ˜ 4 ?m/year Publications: S.P.Fomin et al., Annals of Nuclear Energy, 32 (2005) 1435; Progress in Nuclear Energy, 50 (2008) 163; Atomic Energy, 107 (2009) 288. Conferences: 2001 - QEDSP (Kharkov, Ukraine); 2003 - ICAPP (Cordoba, Spain); 2005 - ICENES (Brussels, Belgium), IAEA-ADS (Minsk, Belarus); 2006 - QEDSP (Kharkov, Ukraine), ICAPP (Reno, USA), COI – INES (Yokohama, Japan); 2007 - PINP WS (St-Perersburg, Russia), ICAPP (Nice, France), IAEA-ADS (Roma, Italy), 2008 - Channeling (Erice, Italy); 2009 - IAEA-ADS (Vienna, Austria), Global 2009 (Paris, France); 2010 - IAEA-ADS (Mumbai, India), ICAPP (San Diego, USA) 2. Design and Analyses of KIPT Electron Accelerator Driven Subcritical Assembly Facility Concept Background A conceptual design of an accelerator driven subcritical assembly has been developed using the existing electron accelerator of Kharkov Institute of Physics and Technology (KIPT) within the cooperative activity between Argonne National Laboratory (ANL) and KIPT. Facility Objectives Provide capabilities for carrying basic and applied research utilizing the radial neutron beam ports of the subcritical assembly. Produce medical isotopes and provide neutron source for performing neutron therapy procedures. Support the Ukraine nuclear power industry by providing the capabilities to perform physics experiments and to train young specialists. Accelerator Driven Subcritical Assembly Facility Design Concept Main Components • Electron beam from the current KIPT accelerator • Target Assembly for generating neutrons • Subcritical assembly with low enrichment fuel, carbon reflector, and water coolant • Heavy concrete biological shield • Auxiliary equipments including the target and the subcritical assembly coolant loops Target Design Analyses Objective: Maximize the neutron production for the available beam power and define the optimal target configuration. Materials for the target – W and natural U Performance and Design Parameters: Neutron source strength Neutron spatial and energy distributions Energy deposition in the target material Beam radius relative to the target radius Target geometrical configuration Thermal hydraulics results Thermal stress results Target fabrication procedure Exploded Assembly View of the Square Uranium Target Design Subcritical Assembly Analyses The subcritical assembly performance was optimized to enhance and maximize the neutron flux field. Main design parameters of the subcritical assembly configuration: ØNatural uranium target material Ø100 KW Beam power Ø200 MeV Electron energy Ø WWR-M2 fuel design with low enrichment uranium (<20%) Ø2.7 g/cm3 fuel material density ØCarbon reflector ØWater coolant ØAluminum alloy structure Fuel Design Fuel Clad Coolant Sub-Critical Assembly. General View 1- is subcritical assembly tank; 2 - is fuel 1 - are graphite reflector rods; 2 - is target handling machine; 3 - is target assembly; assembly; 3 - are fuel elements; 4 - is grid plate; 4 - is redan; 5 - is in-tank fuel storage. 5 - is in-tank fuel storage. Sub-Critical Assembly. Main Parameters Facility Conceptual Design Overview Range of Use The designed neutron source is expected to be used for research into the following areas: qNew nuclear systems; qNeutron therapy; qProduction of medical isotopes; qRadiation material science; qCondensed state physics; qTraining of specialists in nuclear physics and energy; qCold and ultra-cold neutrons 3. DIAGNOSTIC INSPECTION OF STRESS- DEFORMATION CONDIONS OF VVER-1000 REACTORS VESSEL • The used method is coercive force measurement. The methodic is based on the measurement of coercive force dependence on stress-deformation condition level of mettals. For probe delivery to the vessel a manipulator ??-187 was used, that is used at AES with VVER-1000 for visual and ultrasound ??? ??????????? ? ??????????????? inspection of the reactor. • Results of inspection are shown in Fig. There coercive force distribution and stress-deformation condition are presented as plane colored tape from minimal value (blue) up to maximal value (red) when metall is on the edge of failure. It is easy to determine the rate of stress-deformation condition of any zone of inspected vessel. • With use of the method 5 vessels of Zaporogskaya and Source Ukrainian AESs were inspected and the most stressed places were localized. Probe of coercive force at telescopic pole ??-187-? U Probe of coercive force at a reactor vessel Stress-deformation condition of a cylindrical part of a reactor vessel 4. Behavior of core region of a reactor VVER-1000 ??? at heavy accident The main objectives of the project: • to obtain melts of standard VVER fuel and absorber rods, namely combination of UO2, the alloy Zr1%Nb (E110), stainless steel, boron carbide; • to study the effects of fuel and absorber rod structural features (close contact, presence of oxides on the surface) on the nature of the beginning of their materials' interaction and interaction of first and second types of melts, to obtain data on the temperature parameters of the beginning of melt formation as a function of material state; • to study processes of melt formation for new combinations of absorber materials B4C, Dy2O3•TiO2, Hf and interaction of these components with the melt of fuel materials; • to identify phase composition of melts thus formed; • to identify melt viscosity and fluidity parameters depending on their phase composition. 5. Quasi-Monochromatic Compton X ray source eg0 2 2 ec[keV]=0.665B [T]E0 [GeV] eg »4g eg m 0 a0 q e- g eg e- e- E0 e- eg»33 KeV LESR SR source eg0=1.164 eV B0=7.5 T E0=43 MeV E0=2.5 GeV Main Facility Parameters Parameter Value Storage ring circumference, m 15.418 Electron beam energy range, MeV 40-225 Betatron tunes Qx, Qz 3.155; 2.082 Amplitude functions bx, bz at IP, m 0.14; 0.12 Linear momentum compaction factor a1 0.01-0.078 RF acceptance, % > 5 RF frequency, MHz 700 RF voltage, MV 0.3 Harmonics number 36 Number of circulating electron bunches 2; 3; 4; 6; 9; 12; 18; 36 Electron bunch current, mA 10 Laser flash energy
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