Post on 20-Jul-2016
description
Design of Collimator in The Radial Piercing Beam Port of Kartini Reactor for Boron Neutron
Capture Therapy
M. Ilma Muslih A, S.T.
Yogyakarta - June 11, 2014
I N T R O D U C T I O NBoron Neutron Capture Therapy
Medical patient was injected by boron compound before exposing Neutron thermal will be captured by Boron on cancer cell and selectively irradiate cancer cells that have taken up a sufficient amount of Boron and simultaneously spare normal cells
The products of this reaction have high linear energy transfer characteristics (α particle = 150 keV/µm, Lithium-7 = 175 keV/µm )Alpha Radiations will destruct the cancer cell without hurt another healthy tissues
NEUTRON SOURCE I AEA - Requ i remen t
Targeted Cells in deep area need neutron thermal to be captured by boron. Hence, its required epithermal neutron to accomodate moderation effect
If the beam intensity is less than required, exposing timing can be extended. it makes the others beam quality component values increasing. For that reason, beam quality is provided in ratio with epithermal comparison
0.5 eV
10 keVFast
Epitermal
Termal
Beam Intensity
Beam Quality
RADIAL PIERCING BEAMPORTKartini Nuclear Reactor as Neutron Source for BNCT
15 cm 19 cm
156 cm117 cm
Reactor Core (Part 1) (Part 2)
PART OF COLLIMATORFor Boron Neutron Capture Therapy
1. Collimator Wall
2. Moderator
3. Thermal Filter
4. Gamma Shield
5. Aperture (Output)
1. To keep the neutron flux stay high
2. To reduce the fast neutron and Contribute epithermal neutron (Shifting Methode)
3. To Absorb thermal neutron (Filtering Methode)
4. To Attenuate Gamma Ray5. To Control beam Convergenity
MODELING & VALIDATIONKartini Nuclear Reactor using MCNP-5
Nuclear Reactor Critical Conditionkeff = 1,000 + 0,010
Criticality Result of Simulationkeff = 1.0008 ±0.0007
Flux Evaluation
Fuel Ring Simulation( X 1012 )
Reality( X 1012 )
B 1.52 1.78
C 1.37 1.56
D 1.27 1.14
E 1.13 1.14
F 1.21 1.12
According the data, Error of the parameter beetween simulation model result from MCNP-5 is relatively close with Field Experiment.
This reactor model is feasible to be neutron source in Collimator designing using MCNP-5
MATER IALSummary of Collimator component
Collimator Part Recommendation material Best Availability
Collimator Wall Pb, Bi, PbF2 , Ni Ni (95 %)
Moderator Al, Al2O3, dan AlF3 Al 1350 (99.5 %)
Gamma Shield Pb, Bi PbFilter x 6Li , 10B , 60Ni -Aperture Pb, Bi, PbF2 , Ni Ni (95 %)
Additional Safety Control
Boral Boral
Mechanical Engineering UNY partnership
Some material is unavailable in indonesia, especially the pure version. In this case, we use another material with impurity that can subtitute the pure version
COLLIMATOR WALLOptimation material and thickness
0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 50
0.5
1
1.5
2
2.5
3
3.5
4
Fluks neutron epitermal Vs Collimator wall thickness of variation material
PbPolynomial (Pb)BiPolynomial (Bi)PbF2Polynomial (PbF2)NiPolynomial (Ni)
Collimator wall thickness (cm)
Φep
i (n/
cm2)
x 1
09
0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 6 6.50
0.5
1
1.5
2
2.5
3
Fluks neutron epitermal Vs Collimator wall thickness of Ni 95%
Collimator wall thickness (cm)
Φep
i (n/
cm2)
x 1
09
Unsure Isotop (NA) % σa barn
Ni – nat
58Ni (68.07%) , 60Ni (26.23%),
61Ni (1.14 %), 62Ni (3.64%),64Ni (0.926%),
95 4.619
Mn - 55 55Mn (100%), 1.5 13.4118
Fe - nat54Fe (5.8%) , 56Fe (91.72%),57Fe (2.2 %), 58Fe (0.28%), 1 2.585
Si - nat28Si (92.23%) , 29Si
(4.67%),30Si (3.1 %),
0.5 0.1691
Cu - nat 64Cu (69.15%), Cu (30.9%) 1 4.4678C - nat 12C (98.9%), 13C (1.1%) 0.5 0.0034
Ti – nat 46Ti (8.0%), 47Ti (7.3%),
48Ti (73.8%), 49Ti (5.5%), 50Ti (5.4%)
0.5 17.294
Material Impurity
in 95 % of nickel, there is a shifting of peak point flux optimation
Several unsure in this material have greater absorption cross section than nickel. it makes shifting of peek point optimation happened.
MODERATOROptimation material & thickness
5 10 15 20 25 300
1
2
3
4
5
Al Thickness (cm)
df/Φ
epi
x 10
-3
Thickness(cm) Φepi Ḋf / Φepi
5 1.16E+09 3.11E-11
6 1.5E+09 2.59E-11
7 7.72E+08 4.53E-11
8 1.96E+09 1.47E-11
5 1.16E+09 3.11E-11
6 1.5E+09 2.59E-11
7 7.72E+08 4.53E-11
8 1.96E+09 1.47E-11
9 1.47E+09 1.11E-11
10 1.07E+09 1.99E-11
Thickness (cm) Φepi Ḋf / Φepi
11 5.32E+08 5.56E-11
12 8.46E+08 3.42E-11
13 1.15E+08 9E-11
14 2.77E+08 8.45E-12
15 5.57E+08 7.1E-13
16 2.49E+08 2.47E-12
17 2.43E+08 1.63E-11
18 2.99E+08 1E-11
19 2.03E+08 4.53E-11
20 1.96E+08 9.83E-12
Al 1350 (99.5 %)
In this section, we were not only analyse the Fast neutron dose rate per epithermal flux, but also ephitermal neutron Flux it self
GAMMA SHIELDOptimation material & thickness
Thickness (cm) Φepi Ḋγ / Φepi
Without Pb 5.57E+08 1.51E-11Pb 0.5 5.06E+08 1.44E-12
Pb 1 cm 4.05E+08 1.16E-13Pb 1.5 cm 4.02E+08 1.16E-13
Thickness (cm) thermal epithermal Fast total
0.5 2.53E+05 8.21E+06 1.20E+07 2.05E+07
1 1.32E+05 5.88E+06 1.47E+07 2.07E+07
1.5 9.11E+04 9.84E+06 1.40E+07 2.40E+07
2 8.21E+04 8.64E+06 1.23E+07 2.11E+07
Aperture Surrounding
Thicknes (cm) Φepi Ḋf / Φepi Ḋγ / Φepi
0.5 5.12E+08 2.58E-13 1.20E-13
1 5.06E+08 2.49E-13 1.17E-13
1.5 5.03E+08 2.17E-13 1.16E-13
2 4.82E+08 2.26E-13 8.14E-13
Aperture Hole
BORAL ADDITIONALBoron – Aluminum
FINAL RESULTof Collimator Design & Optimation
Parameter Value IAEA RequirementΦepi (n/cm2s) 5.03 x 108 > 1,0 x 109
Ḋf / Φepi (Gy-cm2 /n) 2.17 x 10-13 < 2,0 x 10-13 Ḋγ / Φepi (Gy-cm2 /n) 1.16 x10-13 < 2,0 x 10-13
Φth / Φepi 0.120 < 0,05 J / Φepi 0.835 > 0,7
Minimum Requirement
Of Flux
Petten (NL) Espoo (Fin) Bariloche (Argt) Tokai (Jpn) Hsinchu (Taiwan)
Yogyakarta (Ina)
0
0.5
1
1.5
2
2.5
3
3.5
4
4.5
5
Neutron Flux
comparison
ANOTHER FACILITIESof BNCT therapy in the world
Petten (NL) Espoo (Fin) Bariloche (Argt) Tokai (Jpn) Hsinchu (Taiwan) Yogyakarta (Ina)0
5
10
15
20
25
30Beam Qualitycomparison
Maximum gamma dose contamination
Minimum fast neutron dose contamination
Maximum thermal/epi ratio
ANOTHER FACILITIESof BNCT therapy in the world
Thank’s for your attention
Al - 27 C-Nat S-32 (95.02 %) Al2 O3 AlF3 Al2S3 D2O H2O CF20
5
10
15
20
25
30
35
40
45
50
Material Neutron Cross section Moderator (barn)
tampang lintang hamburan cepat tampang lintang hamburan epitermaltampang lintang serapan Cepat tampang lintang serapan Epitermal
Scaterring cros section
redgreenbluepurpleLgreensoilredgreenbluepurpleLgreensoil
Thermal filter material absorb cross section
Aluminum 99.5 %Densitas Total (g/cm3)= 2.703245
Volume (cm3) = 3015.929
Massa (g) = 8152.796
No. Penyusun % berat Densitas Fraksi/ Densitas
1 Al 99.5 2.7 0.368519
2 Si 0.1 2.329 0.000429
3 Fe 0.4 7.874 0.000508
4 Cu 0.05 8.94 5.59E-05
5 Mn 0.01 7.21 1.39E-05
6 Ti 0.01 4.506 2.22E-05
7 Ga 0.03 5.91 5.08E-05
8 V 0.01 6 1.67E-05
9 Zn 0.05 7.14 7E-05
10 B 0.05 2.08 0.00024