US2023126701A1PendingUtilityA1
Neutron capture treatment device
Assignee: NEUBORON THERAPY SYSTEM LTDPriority: Jul 3, 2020Filed: Dec 16, 2022Published: Apr 27, 2023
Est. expiryJul 3, 2040(~13.9 yrs left)· nominal 20-yr term from priority
A61N 5/1048A61N 5/1065A61N 2005/1092A61N 2005/1074A61N 2005/109A61N 5/1071A61N 5/1077A61N 5/1064A61N 5/1067A61N 2005/1095A61N 5/103A61N 5/1031Y02E30/30G01T 3/06
71
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Claims
Abstract
A neutron capture treatment device includes a neutron beam irradiation system, a detection system, and a correction system, the neutron beam irradiation system being used for producing neutron beams, the detection system being used for detecting irradiation parameters during the neutron beam irradiation treatment, and the correction system being used for correcting a preset neutron dosage; the accuracy of the neutron beam dosage irradiated to a sick body is thereby ensured at the source.
Claims
exact text as granted — not AI-modifiedWhat is claimed is:
1 . A neutron capture treatment device, comprising
a neutron beam irradiation system configured to generate a neutron beam, a detection system configured to detect irradiation parameters during a neutron beam irradiation therapy, and a correction system configured to correct a preset neutron dosage.
2 . The neutron capture treatment device of claim 1 , wherein correction coefficients used by the correction system comprise a neutron correction coefficient K 1 and a boron correction coefficient K 2 .
3 . The neutron capture treatment device of claim 2 , wherein the detection system comprises a neutron dosage detection device configured to detect a dosage of the neutron beam in real time and a boron concentration detection device configured to detect a boron concentration in an object to be irradiated.
4 . The neutron capture treatment device of claim 2 , wherein the correction system obtains the neutron correction coefficient K 1 according to a real-time neutron dosage rate deviation and a positioning deviation of an object to be irradiated.
5 . The neutron capture treatment device of claim 4 , wherein the neutron correction coefficient K 1 is calculated by using a formula (3-1), a formula (3-2) and a formula (3-3) as follows:
K
1
=
K
p
·
K
i
(
3
-
1
)
K
p
=
D
D
0
(
3
-
2
)
K
i
=
I
I
0
(
3
-
3
)
wherein K p is a positioning correction coefficient, K i is a neutron beam intensity correction coefficient, D is a real-time neutron dosage measured by a neutron dosage detection device, D 0 is an uncorrected preset neutron dosage, I is a real-time neutron dosage rate measured by the neutron dosage detection device, and I 0 is a theoretical beam intensity.
6 . The neutron capture treatment device of claim 2 , wherein the correction system obtains the boron correction coefficient K 2 according to a neutron flux and a real-time boron concentration in an object to be irradiated.
7 . The neutron capture treatment device of claim 6 , wherein a first boron concentration value in the object to be irradiated is obtained by a boron concentration detection device, the neutron beam is irradiated into a tumor part by a first track, and a first boron correction coefficient is obtained by the correction system; a second boron concentration value in the object to be irradiated is obtained by the boron concentration detection device, the neutron beam is irradiated into the tumor part by a second track, and a second boron correction coefficient is obtained by the correction system, and wherein the first boron concentration value is greater than the second boron concentration value, the first track is less than the second track, and the first boron correction coefficient is less than the second boron correction coefficient.
8 . The neutron capture treatment device of claim 7 , wherein the boron correction coefficient K 2 is calculated by using a formula (3-4), a formula (3-5) and a formula (3-6) as follows:
K
2
=
K
b
·
K
S
(
3
-
4
)
K
b
=
B
B
0
(
3
-
5
)
K
S
=
φ
B
φ
B
0
(
3
-
6
)
where K b is a boron concentration correction coefficient, K s is a boron self-shielding effect correction coefficient, B is a real-time boron concentration detected by the boron concentration detection device, B 0 is a boron concentration set value in a therapy plan, φ B is a thermal neutron flux in the object to be irradiated when a boron concentration distribution is B, and φ B0 is a thermal neutron flux in the object to be irradiated when a boron concentration distribution is B 0 .
9 . The neutron capture treatment device of claim 8 , wherein the uncorrected preset neutron dosage D 0 is calculated by using a formula (3-7) as follows:
D 0 =D B ·B con ·CBE+D f ·RBE n +D th ·RBE n +D r ·RBE r (3-7)
where D B is a dosage at the boron concentration of 1 ppm and has a unit Gy, B con is an actually measured boron concentration and has a unit ppm, D f is a fast neutron dosage and has a unit Gy, D th is a thermal neutron dosage and has a unit Gy, RBE n is a Relative Biological Effectiveness (RBE) of the neutron, D r is a gamma dosage and has a unit Gy, and RBE r is a gamma RBE.
10 . The neutron capture treatment device of claim 8 , wherein a corrected preset neutron dosage D total is calculated by using a formula (3-8) as follows:
D total =K 1 ·( K 2 ·D B ·B con ·CBE+D f ·RBE n +D th ·RBE n +D r ·RBE r ) (3-8)
where D B is a dosage at the boron concentration of 1 ppm and has a unit Gy, B con is an actually measured boron concentration and has a unit ppm, D f is a fast neutron dosage and has a unit Gy, D th is a thermal neutron dosage and has a unit Gy, RBE n is a Relative Biological Effectiveness (RBE) of the neutron, D r is a gamma dosage and has a unit Gy, and RBE r is a gamma RBE.
11 . The neutron capture treatment device of claim 5 , wherein a neutron dosage detection device comprises a detector configured to receive the neutron beam and output a signal, a signal processing unit configured to process the signal output from the detector, a counter configured to count a signal output from the signal processing unit to obtain a counting rate, a conversion unit configured to convert the counting rate recorded by the counter into a neutron flux rate or a neutron dosage rate, an integration unit configured to integrate the neutron flux rate or the neutron dosage rate to obtain the real-time neutron dosage, and a display configured to display the real-time neutron dosage.
12 . The neutron capture treatment device of claim 8 , wherein the boron concentration detection device detects γ-ray generated by reaction between the neutron and boron, to measure the boron concentration, and a boron distribution measurement system capable of measuring a single-energy γ-ray to measure distribution of the boron concentration is used as the boron concentration detection device.Join the waitlist — get patent alerts
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