Neutron dosimeter
View Patent ↗The invention relates to a neutron dosimeter comprising a neutron moderator ( 12 ), a first radiation detector ( 14 ), which is situated in the neutron moderator ( 12 ) and is surrounded by a first metal body ( 28 ) containing material that can be activated by neutrons, a second radiation detector ( 16 ), which is situated in the neutron moderator ( 12 ) close to the first radiation detector ( 14 ) and is surrounded by a second metal body ( 30 ) that substantially cannot be activated by neutrons. The first metal body ( 28 ) and the second metal body ( 30 ) are designed in such a way that they substantially have the same degree of absorption of photons. The dosimeter also comprises an evaluation circuit, which is connected to the radiation detectors and is equipped to suppress electrical impulses generated by ionising radiation using a pulse intensity that lies below a predefined pulse intensity threshold.
1. A neutron dosimeter with
(a) a neutron moderator ( 12 ),
(b) a first radiation detector ( 14 ),
which is arranged in the neutron moderator ( 12 ) and
surrounded by a first metal body ( 28 ) comprising a silver foil,
(c) a second radiation detector ( 16 ), which
is arranged in the neutron moderator ( 12 ) in the direct vicinity of the first radiation detector ( 14 ) and
is surrounded by a second metal body ( 30 ) comprising a tin foil,
(d) wherein the first metal body ( 28 ) and the second metal body ( 30 ) are designed such that they substantially have the same photon absorption, and
(e) an evaluation circuit, which is connected to the radiation detectors,
(f) wherein the evaluation circuit is designed to suppress electric pulses that are caused by ionizing radiation and have a pulse height that is below a prescribed pulse-height threshold.
2. The neutron dosimeter as claimed in claim 1 , having
(g) a third radiation detector ( 18 ),
which is arranged in the neutron moderator ( 12 ) and
surrounded by a third metal body ( 32 ) containing material that can be activated by neutrons, and
(h) a fourth radiation detector ( 20 ),
which is arranged in the neutron moderator ( 12 ) and
surrounded by a fourth metal body ( 34 ) that substantially cannot be activated by neutrons,
(i) wherein the radiation detectors are arranged symmetrically.
3. The neutron dosimeter as claimed in claim 2 , wherein the radiation detectors are arranged rotationally symmetrically.
4. The neutron dosimeter as claimed in claim 2 , having an evaluation unit, which is designed to carry out a method automatically, the method comprising the steps of:
(i) registering count rates from the radiation detectors,
(ii) calculating the count rate resulting from beta radiation from, firstly, the count rate from the first ( 14 ) radiation detector and, optionally, the third radiation detector ( 18 ) and, secondly, the count rate from the second radiation detector ( 16 ) and, optionally, the fourth radiation detector ( 20 ).
5. The neutron dosimeter as claimed in claim 1 , wherein the pulse-height threshold lies at more than 300 keV.
6. The neutron dosimeter as claimed in claim 5 , wherein the evaluation circuit is designed to suppress electric pulses that are caused by ionizing radiation and have a pulse height that is above a prescribed, second pulse-height threshold, wherein the second pulse-height threshold lies at least at 1000 keV.
7. The neutron dosimeter as claimed in claim 1 , wherein at least one of the radiation detectors is a semiconductor detector.
8. The neutron dosimeter as claimed in claim 1 , wherein the pulse-height threshold lies at more than 600 keV.
9. The neutron dosimeter as claimed in claim 1 , wherein the evaluation circuit is designed to suppress electric pulses that are caused by ionizing radiation and have a pulse height that is above a prescribed, second pulse-height threshold, wherein the second pulse-height threshold lies below 1000 keV.
10. A method for measuring a neutron dose, comprising the following steps:
(a) registering count rates using a first radiation detector ( 14 ),
which is arranged in a neutron moderator ( 12 ) and
surrounded by a first metal body ( 28 ) containing material that can be activated by neutrons,
(b) registering count rates using a second radiation detector ( 16 ),
which is arranged in the neutron moderator ( 12 ) in the direct vicinity of the first radiation detector ( 14 ) and
surrounded by a second metal body ( 30 ) that substantially cannot be activated by neutrons,
wherein the first metal body ( 28 ) and the second metal body ( 30 ) are designed such that they substantially have the same photon absorption, and
(c) establishing the neutron dose from the count rates by
calculating the count rate resulting from beta radiation from, firstly, the count rate from the first radiation detector ( 14 ) and, secondly, the count rate from the second radiation detector ( 16 ) and
calculating the neutron dose from the count rate resulting from beta radiation,
(d) wherein registering the count rates using the first radiation detector ( 14 ) and the second radiation detector ( 16 ) comprises a suppression of count events below a prescribed pulse-height threshold.
11. The method as claimed in claim 10 , wherein the pulse-height threshold lies above 600 keV.
12. The method as claimed in claim 10 , wherein the pulse-height threshold lies at more than 300 keV.