Preliminary design of fission target R&D on UC2 target
First result from IRENA ion source (C. Lau)
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Baseline parameters of the MMW Hg target
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Sketch of the target/ion source system Ion source Insulator
Extraction
Drift tube
RIB out
Heater & thermal shielding
UC2 target Water cooled vacuum chamber
BeO reflector
Hg proton EURISOL-DS: Task#4
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General assumption:
Target length
50 cm
Target dia.
42 cm (in.) – 60 cm (out.)
UC2 material
density 11,4 gcm-3 (238U, natU, reactU)
Layer thickness
1 mm
Target thickness
6 cm
Reflector BeO
thickness 10 cm
FLUKA calculation
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238U
without reflector
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Fission density/incident proton
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natU
with reflector Fission density/incident proton
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natU
without reflector
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Fission density/incident proton
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reactU
with reflector
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Fission density/incident proton
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reactU
without reflector
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Fission density/incident proton
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Fission rate without reflector Fission rate with reflector
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Power deposit in the target
450
Without reflector
400
350
HD (11,4)
HD (11,4)
350
LD (3)
300 without refl 3
]
with refl
250
Power density [W/cm
Total power [kW]
300
200 150 100
250
200
150
100
50 50 0 238
nat
react
0 238
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react
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Total weight (ion source & extraction excluded):
UC2 (11,4 g/cm3)
248
kg
Vacuum chamber & flangies
440
kg
Container & heater
68,5 kg
Graphite
71,6 kg
BeO
183
kg
TOTAL > 1010 kg
Plutonium (ORIGEN)
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290 g (60 days)
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Uranium Target weight
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Effusion calculation (by M. Barbui)
The simulation is performed using the GEANT4 toolkit (NIM A 506(2003),250-303). The isotopes of different mass (A) are simulated by alpha particles with the proper thermal energy. Eth=3/2(8.615*10-5) T 4/A The temperature is T = 2273 K. EURISOL-DS: Task#4
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Geometry 18 lamellas
3 cm 7 cm 50cm
1.6 cm EURISOL-DS: Task#4
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Preliminary results Exit, back open Isotopes considered: 81Ga, 90Kr, 131In 132Sn. Average number of bounces before exit: 54000 A lot of times the nuclei bounce on the lamella surfaces. In a first approssimation we assume for the lamellas the same sticking time of the walls. EURISOL-DS: Task#4
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Preliminary results/low statistics
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Preliminary results/low statistics
Ion
Effusion efficiency
Diffusion efficiency
Ionization efficiency
Total efficiency
132Sn (39,7 s)
0.89
0.19
0.1
0.017
90Kr (32.3 s)
0.99
0.16
0.95
0.15
81Ga (1,22 s)
0.6
0.018
0.4
0.0043
1321In (0.35 s)
0.8
0.056
0.1
0.0045
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Disks UCx 1 15 mm
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Alternative solution
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RFQ - cooler
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Comparison between PARRNe and Gatchina Uranium Carbide
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Preliminary results PARRNe Uranium Carbide: Faster than Gatchina UC2 Follow diffusion law Yields about a factor 2 more efficient for short-lived nuclei EURISOL-DS: Task#4
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Preliminary conclusions
Barrel target seems in part satisfing the requirements Need more detailed estimations on the total release efficiency Because of its weight vertical geometry is suggested Both versions, LD and HD uranium carbide, are suitable Target thickness of 3 cm seems sufficient (both with/without reflector) Low voltage extraction will semplify the target/source assembly Construction of a sector as a prototype R&D on Uranium Carbide targets is in progress at Gatchina 1 PhD position at LNL (3 years) EURISOL-DS: Task#4
Preliminary consideration: a remote handling system close to the SNS solution ... /h. ] Fe. Al. Ceramic. Cd. Cu. Ir. Steel. Ta. W. 1.0E-07. 1.0E-06. 1.0E-05. 1.0E-04.
Oct 27, 2005 - SNS Experimental Facilities Division. Oak Ridge National Laboratory managed by UT-Battelle. EURISOL and SAFERIB Radiation Protection ...
The conformity of the proposed installation to the legislation shall be insuredâ. .... decommissioning-dismantling strategy and cost estimates. ⢠choice of technical ...
numerical tools) to perform the. EURISOL direct target design study. Experiments are under way to validate the design choices. The Feasibility Report about the.
The report in preparation contains an overview on legal aspects concerning conventional toxicity of ... In addition to EURISOL feasibility study, report App. B, an.
Oct 28, 2005 - Nuclear Safety and Control Regulations: 1. ..... excreted per unit intake .... po208 po209 po210 po211 po212 po213 po214 po215 po216 ..... Radiation Protection and Public Health, OECD Nuclear Energy Agency, November ...
Jul 8, 2005 - dE (mbarn/MeV/sr). Fe(p,xn)X à E p ... Production Rate, Atoms/. µ. C ... of atom s. The best models should be used! volatiles. Charge Z. 1013Bq/ ...
Mar 6, 2007 - human capital accumulated through workplace training by 10% would yield ...... Bartel, A.P. (2000), âMeasuring the Employer's Return on Investments in ... Berger, L.M. and J. Waldfogel (2004), âMaternity Leave and the ...
Investigation of high voltage resistivity of insulators. ISOLDE ... Study on soil/ground water activation and activity transport with ground ... Report on task T-J10-1.
Experimental Data of Deep-Penetration Neutrons through a Concrete and Iron. Shield at the ISIS Spallation Neutron Source Facility using an 800-MeV Proton.
Oct 26, 2005 - Overview on Task #3. ⢠Beam sharing ... Pulse selection: 0 to 12 ... 20 ms. Switch between high power and low power targets within one pulse ...
Oct 28, 2005 - Measurements with known tracer elements. 1st year plan: ⢠(B1) design of gas purification system & cryogenic trap prototype commissioning.
Oct 13, 2006 - ... Vamanu, MSc. Model implementation, software design & development ... pathways, including the air, the water, and the food chain. WHY?
cos(. 2. 2. 2. / θ θ gas gas r. T. Twall. TT. â. â. =α. T wall. T gas. T r. 2. VT. â. Hypothesis : 1. Discrete calculus. 2.a. α constant. 2.b. Or non constant. M1C1. M1C2 ...
The FLUKA simulation was done only up to the time of neutron capture, because the current ..... Journal of Nuclear Materials 296 (2001) 83-89. ... 16: Cross sections employed in ralentE.f for carbon and hydrogen (read in from modeff.dat), Gd ...
target station see next slides and detailed results in: M. Felcini, Note EURISOL DS/ TN-06-XX, âOptimized radiation shield design for the EURISOL multi-MW ...
Jan 31, 2006 - uranium carbid e , in w h ic h isotop e s will b e produc e d by t he n e utron-induc ..... 234. 236. 238. 240. Mass number A. Ratio Ï fluka. /Ï data.
