Neutron dose measurement apparatus and neutron capturing treatment device
Disclosed are a neutron dose measurement apparatus and a neutron capturing treatment device. The neutron dose measurement apparatus includes a measurement unit for receiving neutrons and outputting signals, a signal processing unit for processing the signals output from the measurement unit, a counter for counting the signals output from the signal processing unit to obtain a count rate, and a count rate correction unit for correcting the count rate.
1. A neutron dosage detection apparatus, comprising
a detector configured to detect a neutron 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, and
a counting rate correction unit configured to correct the counting rate, wherein the counting rate correction unit calculates a corrected counting rate C k by using formulas (1-1) and (1-2):
C
k
=
K
·
C
t
(
1
‐
1
)
K
=
m
n
(
1
‐
2
)
where K is a counting rate correction factor, C t is a real-time counting rate recorded by the counter, n is the number of pulses recorded by the counter in unit time, and m is the number of signal pulses actually generated within the detector in unit time.
2. The neutron dosage detection apparatus of claim 1 , wherein the counting rate correction unit derives a formula (1-4) by combining the formula (1-2) with the formula (1-3), to calculate the counting rate correction factor K:
m
-
n
=
nm
τ
(
1
‐
3
)
K
=
1
1
-
n
τ
(
1
‐
4
)
where τ is a pulse resolution time.
3. The neutron dosage detection apparatus of claim 2 , wherein the counting rate correction unit calculates the pulse resolution time τ by using a formula (1-5):
τ
=
I
2
I
1
·
C
1
-
C
2
I
2
I
1
·
C
1
·
C
2
(
1
-
5
)
where I 1 is a first neutron beam flux, C 1 is a counting rate recorded by the counter when a neutron beam flux is I 1 , I 2 is a second neutron beam flux, C 2 is a counting rate recorded by the counter when a neutron beam flux is I 2 .
4. The neutron dosage detection apparatus of claim 1 , wherein the detector comprises one or more of a He-3 proportional counter, a BF 3 proportional counter, a fission chamber, a boron ionization chamber or a scintillator detector.
5. The neutron dosage detection apparatus of claim 1 , further comprising a conversion unit configured to convert the counting rate into a neutron flux rate or a neutron dosage rate, and an integration unit configured to integrate the neutron flux rate or the neutron dosage rate to obtain a neutron dosage.
6. The neutron dosage detection apparatus of claim 5 , further comprising a display configured to display the neutron dosage.
7. A neutron capture therapy device, comprising the neutron dosage detection apparatus of claim 1 .
8. The neutron capture therapy device of claim 7 , comprising a neutron beam irradiation system, the neutron beam irradiation system comprises a neutron beam generation module configured to generate a neutron beam, and a beam adjustment module configured to adjust the neutron beam and comprising a retarder configured to decelerate the neutron beam and a reflector configured to guide a deviated neutron back to the retarder.
9. The neutron capture therapy device of claim 7 , wherein the counting rate correction unit derives a formula (1-4) by combining the formula (1-2) with the formula (1-3), to calculate the counting rate correction factor K:
m
-
n
=
nm
τ
(
1
‐
3
)
K
=
1
1
-
n
τ
(
1
‐
4
)
where τ is a pulse resolution time.
10. The neutron capture therapy device of claim 9 , wherein the counting rate correction unit calculates the pulse resolution time t by using a formula (1-5):
τ
=
I
2
I
1
·
C
1
-
C
2
I
2
I
1
·
C
1
·
C
2
(
1
‐
5
)
where I 1 is a first neutron beam flux, C 1 is a counting rate recorded by the counter when a neutron beam flux is I 1 , I 2 is a second neutron beam flux, C 2 is a counting rate recorded by the counter when a neutron beam flux is I 2 .
11. The neutron capture therapy device of claim 7 , wherein the detector comprises one or more of a He-3 proportional counter, a BF 3 proportional counter, a fission chamber, a boron ionization chamber or a scintillator detector.
12. The neutron capture therapy device of claim 7 , further comprising a conversion unit configured to convert the counting rate into a neutron flux rate or a neutron dosage rate, and an integration unit configured to integrate the neutron flux rate or the neutron dosage rate to obtain a neutron dosage.
13. The neutron capture therapy device of claim 12 , further comprising a display configured to display the neutron dosage.