Planning and preparation approaches for non-nuclear waste disposal
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1 Planning and preparation approaches for non-nuclear waste disposal Lucia Sarchiapone Laboratori Nazionali di Legnaro (Pd) Istituto Nazionale di Fisica Nucleare INFN
2 Outline Laboratori Nazionali di Legnaro The SPES Project Expected levels of radioactivity, studies: The irradiation target The shielding structure Approach for the disposal NEA Workshop on the Management of Non-nuclear Radioactive Waste 2
3 NEA Workshop on the Management of Non-nuclear Radioactive Waste New building area hosting the cyclotron and the irradiation bunkers Existing acceleration line Linear accelerator ALPI 3
4 The SPES Project (Selective Production of Exotic Species) Radioactive Cyclotron ALPI beams: 90 Rb, 135 I, 137 Te, 138 Xe, 94 Kr, 132 Sn, 134 Sn PIAVE TANDEM RIB: Sn-132 +n, I-135 +n, 9 MeV/amu RIB: Sn-132 +n, I-135 +n, up to 40 kv RIB: Sn , I , up to 40 kv according to mass Protons, 40 MeV 200 ma NEA Workshop on the Management of Non-nuclear Radioactive Waste 4
5 The Cyclotron name: p70 made by: Best Cyclotron energy: MeV maximum current: 750 ua particles: H- special remarks: dual port NEA Workshop on the Management of Non-nuclear Radioactive Waste 5
6 The fissionable target Graphite holder 7 UC 2 disks 1 mm thick Graphite dump Developed by the SPES target group, NEA Workshop on the Management of Non-nuclear Radioactive Waste 6
7 Target ISOL technique beam effusion at work Ionization of the radioactive beam The type of source is related to the final beam NEA Workshop on the Management of Non-nuclear Radioactive Waste A. Andrighetto 7
8 Fluka geometry The target: irradiation cycle and inventory The SPES target is made of 7 UCx disks, 4 cm diameter, 1 mm thickness (about 30 g uranium-238 content) Graphite box Proton beam window UC x disk dumper The irradiation cycle lasts 14 days, a total of protons on target and a total of fissions are induced on the target NEA Workshop on the Management of Non-nuclear Radioactive Waste 8
9 Atomic abundances (atoms per 200 ua) atomic abundance (atoms per 200uA) Atomic number Z Z Atoms atoms per per proton proton Production in production target at in target 40 at MeV 40 proton energy 100 The target: irradiation cycle and inventory Direct fission from 40 MeV protons on UC N Number of neutrons N FLUKA simulation fissions/sec mass number (A) Mass number A Total target activity after 2 weeks irradiation Bq NEA Workshop on the Management of Non-nuclear Radioactive Waste 9
10 The target: irradiation cycle and inventory 14 days protons on target fissions/cycle About 1 kci totally produced in 1 cycle 10% 1% 2% T 1/2 < 1 hour 1 hour < T 1/2 < 1 day 1 day < T 1/2 < 1 month 1 month < T 1/2 < 1 year 1 year < T 1/2 < 10 years T 1/2 > 10 years 17% 70% NEA Workshop on the Management of Non-nuclear Radioactive Waste 10
11 The target: induced radioactivity Bq NEA Workshop on the Management of Non-nuclear Radioactive Waste 11
12 The temporary storage design Small area to store the irradiated targets before their final destination as waste NEA Workshop on the Management of Non-nuclear Radioactive Waste 12
13 Simulation set up Lead and steel box, as designed and realized by the target group at LNL NEA Workshop on the Management of Non-nuclear Radioactive Waste 13
14 Y (cm) RP consideration on temporary storage Gamma dose rate from exhausted targets Ceiling floor X (cm) < 50 msv/h Once filled the rack, targets will shield each other: dose rate below 50 usv/h A concrete wall 50 cm thick will reduce the dose rate by a factor 100 msv/h NEA Workshop on the Management of Non-nuclear Radioactive Waste 14
15 Irradiation process the shielding UC 2 target (30 g) in the form of 7 thin disks. Energy: 40 MeV Current: 200 ma Irradiation period: 20 years Working load: 5000 hours/year target 2 m distant from the wall surface; shielding wall 360 cm wide; UC 2 cylindrical activation sample cut in the wall, radius 3 cm, zero degree parallel to the beam direction p 40MeV 200 ma NEA Workshop on the Management of Non-nuclear Radioactive Waste 15
16 Shielding Material Elemental composition of concrete (r=2.3 g/cm 3 ) used for the shielding of the target hall: Hydrogen underestimated (conservative assumption neutron slowing down effect); Eu and Co important because of their long half lives; Iron percentage does not include that due to the reinforcement rods. Element Atomic Fraction Weight Fraction Hydrogen % Oxygen % Magnesium % Aluminum % Silicon % Calcium % Iron % Europium ppm Cobalt ppm Reinforcement is obtained with a stainless steel grid, with rods of radius 1 cm, spaced by 10 cm. NEA Workshop on the Management of Non-nuclear Radioactive Waste 16
17 cm -2 per proton Neutron fluence p 40MeV 200 ma UC 2 NEA Workshop on the Management of Non-nuclear Radioactive Waste 17
18 Neutron energy Reactions of neutrons with nuclei in the shielding: Thermal neutrons (E < 1 ev) High energy neutrons (E > 20 MeV) NEA Workshop on the Management of Non-nuclear Radioactive Waste 18
19 Neutron energy and radioactive species Some long lived radionuclides are produced by high energy neutrons ( 54 Mn, 22 Na) 54 Mn 54 Fe (n,p) 55 Mn (n,2n) 22 Na 23 Na (n,2n) NEA Workshop on the Management of Non-nuclear Radioactive Waste 19
20 Neutron energy and radioactive species Some radionuclides produced by thermal neutrons: the activity concentration as a function of the depth in concrete resembles that of thermal flux. 46 Sc 45 Sc (n,g) 59 Fe 58 Fe (n,g) 60 Co 59 Co (n,g) 152 Eu 151 Eu (n,g) NEA Workshop on the Management of Non-nuclear Radioactive Waste 20
21 Radioactive species in concrete Following the irradiation of the concrete structure by secondary neutrons, nuclei de-excite by the emission of energetic g-rays; Nuclide Half life 152 Eu 13.5 y 60 Co 5.27 y 59 Fe 44.5 d 56 Co d g-ray energy (kev) Table: Radionuclides with T 1/2 > 1 month. The more energetic g emitters have been included. 54 Mn d Sc d 26 Al y Na y NEA Workshop on the Management of Non-nuclear Radioactive Waste 21
22 Radioactive species in concrete Long lived radionuclides in a sample 20 cm deep from the surface, at the end of the irradiation period (20 years). Nuclide Half life 152 Eu 13.5 y 60 Co 5.27 y Activity (Bq/g) % of the overall activity is due to nuclides with half life longer than 1 year. The nuclides specified in the table are found in the concrete sample. In the rods some of these nuclides can be found (species produced by irradiation of iron, 60 Co, 59 Fe, 55 Fe, 54 Mn) with higher concentrations. 59 Fe 44.5 d Fe 2.73 y Mn d Ca d Al y Na y H y NEA Workshop on the Management of Non-nuclear Radioactive Waste 22
23 Activation and cooling Activity concentration rapidly decays as the depth increases in the first cm. Symbols represent the activity concentration in the rods, while lines represent the same quantity in concrete. As a representative value, 1Bq/g is obtained after 20 years of cooling time in the outer part 185 cm thick. NEA Workshop on the Management of Non-nuclear Radioactive Waste 23
24 Conclusions LNL host particles accelerators for research in nuclear physics New projects and high power involved push for consideration of waste production and planning for disposal Necessary to start the study before civil construction starts, in order to plan places and techniques for future disposal. NEA Workshop on the Management of Non-nuclear Radioactive Waste 24
25 Thank you for your attention L. Sarchiapone Laboratori Nazionali di Legnaro (Pd) Istituto Nazionale di Fisica Nucleare INFN NEA Workshop on the Management of Non-nuclear Radioactive Waste
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