Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA) C. H. Pyeon, T. Misawa, H. Unesaki, K. Mishima and S. Shiroya (Kyoto University Research Reactor Institute, Japan)
Contents Background and Purpose A plan of ADSR (Kart & Lab. Project): Accelerator Driven Subcritical Reactor (ADSR) in Kyoto University Critical Assembly (KUCA) by using Fixed Field Alternating Gradient (FFAG) Accelerator Neutron spectrum experiments by Foil activation method - 14MeV neutron experiment (Pulsed neutron generator) - High-energy proton experiment (FFAG accelerator) ADS collaboration research in Japan IAEA benchmark problem Summary
Background ADS Research and Development: producing energy and transmuting minor actinides and long-lived fission products A neutron source in next generation of KURRI and introduction of a new accelerator Injection of 150MeV proton beam into KUCA core (with Tungsten (W) target) on Aug. 2007 Investigation of main characteristics of ADSR using KUCA core with 14MeV pulsed neutrons generator
Purpose Conduct feasibility study of ADSR in KURRI as Energy Amplifier System Examine subcritical neutronic characteristics through experiments in KUCA (KUCA A core + 14MeV pulsed neutron generator) Assess neutronic characteristics for 14MeV neutrons by MCNP analyses with nuclear data libraries Establish measurement techniques - Reaction rate distribution, Neutron spectrum, etc. - Subcriticality, Neutron multiplication, Neutron decay constant
FFAG Accelerator Ion Generator 100keV 2.5MeV 20MeV 150MeV H + Ion Beta (FFAG Acc.) Booster (FFAG ACC.) Main Ring (FFAG Acc.) KUCA Max. Power : 100W Yield : 1 10 10 n/s Main parameters in the FFAG accelerator # of sectors 12 Energy 2.5-150MeV Repetition rate Average beam current Rf frequency 120Hz 1nA 1.5-4.6MHz Field index 7.5 Closed orbit radius 4.4-5.3m
KUCA A-core & FFAG Accelerator FFAG Accelerator Beam Line KUCA A core
KUCA A-core & 14MeV D-T Accelerator Tritium Target Beam Injection KUCA A-core Accelerator (D-T reactions) - 14MeV Pulsed Neutrons - Yield: 1 10 9 n/s, Intensity: 0.5mA Critical Assembly - Highly enriched 235 U - Polyethylene Reflector & Moderator - Thermal neutron field Cockcroft-Walton type Accelerator
KUCA A-core (with Neutron guide) - KUCA A-core - A solid-moderated and reflected core C3 S5 S4 F F SV F F C1 F F SV F F Polyethylene C2 22 SV 22 S6 59.1cm s' s s s s s s Fuel Cell 36 39.5cm 152.4cm Collimator region b bs bs bs b 0.15874cm(1/16") Enriched Uranium b bs bs bs b 0.3086cm(1/8") Polyethylene 53.8cm f fs fs fs f 0.63cm(1/4") Polyethylene Polyethylene Fuel Aluminum assembly sheath Fig. KUCA A-core with neutron guide Fig. Image of KUCA A-core and fuel assembly loaded
Neutron Spectrum Experiments by 14MeV Neutrons Table Activation foils with threshold energy and size C3 S5 Reaction Threshold [MeV] Size [mm 3 ] S4 C2 F F SV F F F F SV F F 22 SV 22 s' s s s C1 S6 115In (n, n ) 115m In 56Fe (n, p) 56 Mn 27Al (n, α) 24 Na 0.32 2.97 3.25 45 45 3 45 45 5 45 45 5 92Nb (n, 2n) 92m Nb 9.05 45 45 2 197Au (n, γ) 198 Au Normalization 1φ 0.05 s s s b bs bs bs b b bs bs bs b f fs fs fs f Fig. KUCA A-core with neutron guide Irradiation - Positions: Core center and Target - Method: Foil activation method - Irradiation time: 3 to 6 hrs Subcriticality - 0.87, 1.23, 1.75%Δk/k MCNP-4C2 and ENDF/B-VI.2
Reaction Rates Evaluation Core 115 In Table Comparison of measured reaction rates with calculated ones Threshold [MeV] C/E (0.87%Δk/k) C/E (1.23%Δk/k) C/E (1.75%Δk/k) 0.32 2.31 ± 0.05 2.22 ± 0.05 2.10 ± 0.05 56 Fe 2.97 0.14 ± 0.01 0.17 ± 0.01 27 Al 3.25 1.10 ± 0.03 1.05 ± 0.03 93 Nb 9.05 None 0.10 ± 0.01 0.20 ± 0.01 0.92 ± 0.03 None Reaction rates evaluation Good: 27 Al within 10% error regardless of subcriticality Large discrepancy: 115 In, 56 Fe and 93 Nb Relationship between C/E value and subcriticality Target 115 In 56 Fe 27 Al 93 Nb C/E 4.50 ± 0.88 0.13 ± 1.26 0.02 ± 1.29 0.04 ± 0.04
Unfolding Evaluation 10 1 Neutron flux [Arbtrary units] 10 0 10-1 10-2 10-3 10-4 ρ = 1.23 %Δk/k Unfolding (SANDII) Initial guess (MCNP) Numerical analyses - Unfolding by SANDII (based on measured reaction rates) - Initial guess by MCNP (ENDF/B-VI.2) 10-5 10-1 10 0 10 1 Energy [MeV] Fig. Comparison of unfolding with initial guess Good evaluation by unfolding analyses based on measured reaction rates
Neutron Spectrum Experiments at FFAG accelerator 25mm Flange Beam duct Proton beam 500mm 200mm 540mm 750mm W (t = 3mm) 500mm 50 mm Nb (t = 1mm) Bi (t = 3mm) Fig. Top view of PoP FFAG acc. (KEK) Proton beam (At beam dump: 70MeV, 0.4n) 184 W target and 93 Nb (Norm. factor of neutron generation) 209 Bi Threshold Energy (15 to 90MeV): 209 Bi (n, xn) 210-x Bi (x=3 to 12)
Neutrons and Protons Estimation 10-2 Table Measured reaction rates obtained at FFAG acc. Neutron flux [Arbitrary units] 10-3 10-4 10-5 10-6 Proton beam injection 70MeV 80MeV 100MeV Reaction Threshold [MeV] 209Bi (n,3n) 207 Bi 14.42 209Bi (n,4n) 206 Bi 209Bi (n,5n) 205 Bi 209Bi (n,6n) 204 Bi 209Bi (n,7n) 203 Bi 22.55 29.62 38.13 45.37 Measured reaction rate - (1.51 ± 0.01) 10 5 (1.01 ± 0.03) 10 5 (2.37 ± 0.02) 10 4 (6.35 ± 0.16) 10 3 10-7 10-3 10-2 10-1 10 0 10 1 10 2 209Bi (n,8n) 202 Bi 54.24 (2.74 ± 0.07) 10 2 Neutron energy [MeV] Fig. Calculated neutron spectrum evaluated by MCNPX 209Bi (n,9n) 201 Bi 61.69-209Bi (n,10n) 200 Bi 70.89 - About 60MeV neutron generation by about 70MeV proton injection onto 184 W Useful foil of 209 Bi covering wide range of threshold energy 209Bi (n,11n) 199 Bi 78.47-209Bi (n,12n) 198 Bi 87.94 -
ADS Collaboration Research in Japan KURRI (Kart & Lab. project): KUCA, FFAG Accelerator Thermal neutron field Energy amplifier system JAEA (J-PARC project): FCA, TEF-P, TEF-T Fast neutron field Nuclear Transmutation User and support group: Tohoku Univ., Nagoya Univ., Kinki Univ., etc. Subcriticality measurement (Noise method, NSM method, etc.) Neutronic characteristics (Neutron flux, Neutron spectrum, etc.) Nuclear Transmutation (MAs, FPs, etc.) ADSR neutron source (Thermal) KURRI JAEA ADS Test Reactor (Fast) ADS Incineration (Fast) KUCA (Thermal) FFAG Acc. (1Gev) FCA KUCA (Thermal) FFAG Acc. (150Mev) TEF-P TEF-T J-PARC LINAC 800MeV
IAEA Benchmark Problem Phase I: Static experiments (14MeV neutrons) Reaction rates distribution, Neutron spectrum, Reactivity Phase II: Kinetic experiments (14MeV neutrons) Neutron multiplication, Subcriticality measurement method (Rossi-α, Feynman-α, Pulsed neutrons and Neutron source multiplication (NSM) methods) Phase III: Static and Dynamic experiments (150MeV protons) Above topics, γ-ray distribution, Power monitoring, etc. - Fuel: Highly enriched 235 U, 232 Th, Natural Uranium - Reflector: Polyethylene, Graphite, Aluminum, Beryllium - Core: Any combinations of Fuel & Reflector Publish KUCA benchmark problem in a near future
Summary ADSR project (Kart & Lab. project) in KURRI - Energy amplifier system by ADSR Neutron spectrum experiments of ADSR - 14MeV pulsed neutrons in KUCA Reaction rates evaluation: Good results by foil activation method Unfolding evaluation: Feasibility of SANDII code - High-energy protons from FFAG accelerator About 60MeV neutron generation by about 70MeV proton injection onto 184 W target Useful activation foil of 209 Bi covering wide range of threshold From 14MeV neutron results, very important and valuable information, for 150MeV proton analyses
KUCA A-core - KUCA A-core - A solid-moderated and reflected core C3 S5 S4 C2 12 C1 S6 Polyethylene 59.1cm Fuel Cell 36 39.5cm 152.4cm Collimator region 0.15874cm(1/16") Enriched Uranium 0.3086cm(1/8") Polyethylene 53.8cm 0.63cm(1/4") Polyethylene Polyethylene Fuel Aluminum assembly sheath Fig. KUCA A-core (Reference core) Fig. Image of KUCA A-core and fuel assembly loaded
Static Experiments 0.15 C3 S4 C2 F F SV F F F F SV F F 22 SV 22 s' s s s s s s b bs bs bs b S5 C1 S6 Normalized reaction rate [Arb. units] 0.10 0.05 Subcriticality (%Δk/k) 0.68 0.70 0.90 1.34 1.76 Collimator region SV region Fuel region b bs bs bs b f fs fs fs f 0 0 10 20 30 40 50 Distance from target [cm] Fig. Measured Indium reaction rates distribution. Fig. KUCA A-core with collimator and beam duct. Reaction rates distribution (Foil activation method) Measure 115 In (n, γ) 116m In (Exp. error: 5%) Examine effects on subcriticality, configuration Optimize collimator and beam duct
MCNP Analyses for Static Experiments Table Comparison of measured subcriticality with calculated one. 0.10 Experiment (%Δk/k) MCNP (JENDL-3.3) (%Δk/k) MCNP (ENDF/B-VI.2) (%Δk/k) -0.68±0.04-0.68 (1.4%) -0.67 (1.8%) -0.89±0.05-0.98 (5.7%) -0.91 (3.5%) Reaction rate [Arb. units] 0.08 0.06 0.04 0.02 Experiment MCNP (JENDL-3.3) Collimator region SV region Fuel region -1.34±0.07-1.35 (0.3%) -1.40 (3.9%) -1.76±0.09-1.71 (2.9%) -1.72 (2.4%) 0 0 10 20 30 40 50 Distance from target [cm] ( ): Relative difference, Cal. error: 0.03%Δk/k Fig. Comparison of measured In reaction rates distribution with calculated one. MCNP eigenvalue and point source calculations Good evaluation by MCNP within experimental error
Optical Fiber Detection System 1.2 6 Li reaction rate [Arbtrary units] 1.0 0.8 0.6 0.4 0.2 Subcriticality ρ [%Δk/k] 0.41 1.10 2.27 4.03 Core region Reflector region Area ratio method Neutron multiplication M 300.00 200.00 100.00 M eff = 1 / ( 1 - k eff ) M exp-abs (Absolute value) M exp-rel (Relative value) M cal-abs (Absolute value) M cal-rel (Relative value) 0 0 5 10 15 20 25 Distance from the center of core [cm] 0 0 1.00 2.00 3.00 4.00 5.00 Subcriticality ρ (%Δk/k) Fig. Li reaction rates by optical fiber detection system, along to subcriticality. Optical fiber detection system LiF (ZnS): 6 Li (n, α) reaction for thermal neutrons ThO 2 (ZnS): 232 Th fission reaction for fast neutrons Fig. Neutron multiplication by Area ratio method applied to Li reaction rates.
Dynamic Experiments (Optical fiber system) C3 1/2φ F F F F Core F S4 C2 F S6 Reflector S5 C1 Relative Li reaction rate [Arb. units] 10 0 10-1 10-2 - Core - Experiment MCNP LiF fiber - Reflector - Experiment MCNP 10-3 0 0.002 0.004 0.006 0.008 0.01 Time [Sec.] Fig. Measured neutron decay behavior by optical fiber detector system. ThO 2 fiber Pulsed neutron method (PNM) Good evaluation of subcriticality at both core and reflector positions Examine methodology and position dependency
Subcriticality (Source Multiplication Method) BF BF 3 detectors 252 Cf Table Comparison of measured subcriticality with calculated ones (with JENDL-3.3). BF BF C3 S4 F F SV F F S5 C1 Ref. Exp. value (%Δk/k) MCNP (%Δk/k) Higher-mode SM method (%Δk/k) -0.72±0.06-0.69 (4.2%) -0.67 (6.9%) BF C2 F F SV F F 22 SV 22 S6-2.72±0.22-2.88 (5.9%) -2.52 (7.4%) s' s s s -5.96±0.45-6.44 (7.5%) -5.19 (12.9%) s s s -8.66±0.69-10.46 (20.8%) -7.09 (18.1%) b bs bs bs b b bs bs bs b f fs fs fs f ( ): Relative difference, Cal. error: 0.03%Δk/k Subcriticality (Source Multiplication method) Measurement technique Detector position dependency Improvement of precision and methodology