1 Introduction
The reading of a neutron dose equivalent rate meter in a neutron field is attributable to both neutrons that arrive directly from the source to the meter and neutrons scattered from air, concrete walls, and other objects in the calibration room. The scattered component depends on the source type, room materials and configuration, calibration distance, and also the shape and the material composition of the neutron meters [1]. However, different neutron meters could yield different readings for the same total neutron field. Thus, an appropriate calibration process is necessary before this instrument can be used for radiation protection assessment. In the calibration process, the calibration factor (CF) of the neutron meter is evaluated as one of the important characteristics. The CF is defined as the ratio between the conventional true value of the neutron ambient dose equivalent rate in a free field (denoted as
To obtain the value of
In the present work, calibrations were performed for three types of neutron meters, i.e. Aloka TPS-451C (Hitachi), KSAR1U.06 (Baltic Scientific Instruments), and Model 12-4 (Ludlum), in the standard calibration field with a 241Am-Be source at the Institute for Nuclear Science and Technology (Hanoi, Vietnam). The neutron meters were used to measure the values of
2 Instruments and methods
2.1 Neutron calibration field property
A neutron calibration room was constructed with inner dimensions of 7.0×7.0×7.0 m3 [3] and a radionuclide neutron 241Am-Be source of X14 type encapsulation supplied by Hopewell Designs, Inc., USA, was installed in a container at the center of the floor base. The initial source strength was determined at NIST (USA) on January 23, 2015, to have a value of 1.299 × 107 s-1 with the expanded uncertainty of 2.9% (k=2). A detailed description of the neutron calibration room and the 241Am-Be source can be found in previous works [3, 4]. The source anisotropy correction factor is 1.030, which was evaluated at a distance of 100 cm from the source and in a direction perpendicular to the cylindrical source axis using the MCNP5 simulation [4]. This anisotropy correction factor is consistent with the values of 1.027 - 1.030 for similar 241Am-Be sources as reported by other laboratories [5, 6].
2.2 Neutron meters
In the measurements, three portable neutron meters were used as shown in Fig. 1. The Aloka-TPS-451C meter that is made by the Hitachi group consists of a cylindrical proportional counter with a length of 15.5 cm and a diameter of 2.5 cm and filled with 5 atm 3He gas at 20oC. The counter is covered by a cylindrical moderator of high-density polyethylene (ρ=0.95 g/cm3) with a length of 23.0 cm and a diameter of 21.0 cm. The counter has cylindrical effective dimensions of 7.0 cm in length and 2.4 cm in diameter. The Aloka-TPS-451C meter can be used to measure neutrons in the energy range from 25×10-9 to 15 MeV with a dose equivalent rate up to 10 mSv/h. In general, the meter is not sensitive to photons [7].
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The KSAR1U.06 meter that is made by Baltic Scientific Instruments (BSI) enterprise has three cylindrical 3He proportional counters with a diameter of 3.2 cm and a length of 2.0 cm and is filled with 2.7 atm pressure assembled to form a neutron sensitive detector and a photon sensitive Geiger Muller counter. The meter allows for measurement of the ambient dose equivalent rate in the range from 0.28 μSv/h to 700 μSv/h for neutrons and from 0.14 μSv/h to 1400 μSv/h for photons. The KSAR1U.06 meter is produced in compliance with IAEA recommendations and requirements [8]. The outer dimensions of the meter are 30 cm×16 cm×13 cm [9].
The Model 12-4 meter is made by Ludlum Incorporation and consists of a cylindrical proportional counter 3He with a diameter of 1.6 cm and a length of 2.5 cm surrounded by a 22.9 cm diameter cadmium loaded polyethylene sphere. The meter rejects photons up to 100 mSv/h and facilitates the measurement of neutrons from thermal through 7 MeV sources. It provides response up to 12 MeV with a neutron ambient dose equivalent rate up to 100 mSv/h. The meter generates an energy response for an appropriate inverse radiation protection guide curve for neutrons [10].
2.3 Measurements of total neutron ambient dose equivalent rates
In the experiments, the effective points of the neutron meters were placed at the reference point of the neutron field such that the central axis of the Aloka TPS-451C meter was parallel to the base floor and perpendicular to the central beamline at the effective point. The appropriate settings were applied to the other two neutron meters during the measurements. The KSAR1U.06 meter was irradiated from the front side, whereas the Model 12-4 meter was irradiated from the side with the needle analog display facing upwards. Then the values of
In general, the neutron meters based on the 3He gas proportional counters as thermal neutron detectors can detect neutrons by the reaction 3He(n,p)3H (Q = 0.76 MeV) and are not sensitive to photons due to the suitably applied discrimination level [11]. Therefore, the influence of photons on the
2.4 Fit methods
To obtain the
where, k is the characteristic constant; l is the distance from the center of the source to the device center; A’ is the air in-scatter component; s is the factor that accounts for the contribution of all other in-scattered neutrons; rD is the detector radius of the spherical meter or it is considered as half of the minimum dimension for a non-spherical meter; δ = 0.5 is the neutron effectiveness parameter and
The SEM method proposed by Eisenhauer et al. [5, 6] was summarized in ISO 8529-2:2001 [2]. The SEM is based on the assumption that the air-scattered component decreases linearly with distance from the source while the room-scattered component is independent of the distance. Therefore, the
where, A is the net air-scatter effect (in-scatter minus out-scatter) which may appear to be similar to the A’ factor in Eq. (1); R is the room scattered component which is similar to the factor s in Eq. (1). The other parameters such as δ, rD, and k have the same meanings as those in Eq. (1). In the SEM method, k, A and R are free parameters obtained via a fitting process. It is indicated in Ref. [15] that the SEM is well applied in small and intermediate size rooms. It is therefore suggested that the SEM will be useful for the neutron calibration room in this work.
The RFM method is applicable if the measured distance l is greater than or equal to approximately 1.5 times the largest dimension of the meter [16]. Given that in the present work, the measurements were conducted at distances greater than 60 cm, the RFM method is applicable. Based on this assumption, it is considered that the neutron ambient dose equivalent rate due to the room-scattered component, denoted as Rsct, is dominant at most calibration points and is constant in the space of the calibration room. Thus, the
In Eq. (3), the term k/l2 is an important factor which determines the corresponding direct component
3 Results and discussion
3.1 Conventional true value of
The values of
where B is the neutron source strength; F1(θ) is the source anisotropy correction factor which is 1.030 at 1.0 m as reported in a previous work [4]. For the purpose of this work,
3.2 Neutron ambient dose equivalent rates measured by neutron meters
The results of measurements of
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3.3 Fitting parameters
The
Method | Fitting parameters | Neutron dose equivalent rate meter | ||
---|---|---|---|---|
Aloka TPS-451C, Hitachi | KSAR1U.06, BSI | Model 12-4, Ludlum | ||
GFM | k | 1535750 ± 34790 | 1508230 ± 105050 | 1506720± 277450 |
A’(× 10-4) | 0.243 ± 2.985 | 0.000 ± 0.001 | 9.918± 0.004 | |
s(× 10-6) | 9.025 ± 0.729 | 32.631 ± 1.581 | 0.000 ± 0.144 | |
SEM | k | 1528160± 28760 | 1475300 ± 98120 | 1516850 ± 214160 |
A(× 10-4) | 0.002 ± 3.024 | 6.211± 0.002 | 7.855 ± 0.003 | |
R(× 10-6) | 8.875 ± 1.465 | 26.912± 15.630 | 0.001 ± 9.009 | |
RFM | k | 1530730± 6130 | 1500560± 20690 | 1506560 ± 60140 |
Rsct | 13.521± 0.195 | 48.753± 0.888 | 10.500 ± 3.535 |
3.4 Calibration factors and uncertainties
From the definition of CF, the equation of H*(10)FF (Eq. (4)) and the direct term k/l2 in the fitting process, the CF can be expressed as:
The standard uncertainty of the CF (denoted as uCF) can be calculated by applying the uncertainty propagation principle. The uncertainty budgets of the CFs due to type A uncertainty of the fitting characteristic constant (uk) and type B uncertainty of the source strength (uB) are summarized and shown in the Table 2, together with the uCF values. The CFs of each neutron meter corresponding to the three fit methods are in agreement and close to unity (see Fig. 3), even at different levels of uCF (see Table 2). The averaged CFs of the three neutron meters are 0.99 ± 0.01, 1.00 ± 0.03 and 0.99 ± 0.08, respectively. The largest difference in the CFs due to different fit methods is approximately 4.0% and was obtained with the KSAR1U.06 meter using the GFM and SEM methods. For the other cases, the CF of each meter is consistent within 2.0%. This means that the calibration process is reliable. The CFs satisfy the ISO criteria [2] as a unique property of the neutron measuring device and is independent of the characteristics of the facilities and the calibration techniques. The largest uncertainty of the CFs was determined for the Model 12-4 meter, which can be seen in Table 2. It is also evident that the CF uncertainties due to the RFM fit method are the smallest (in the range from 1.50% to 4.23%) compared to that obtained using the two other methods. This is described as a simple form of the fitting equation (Eq. (3)), where the constant Rsct is consistent with the statement of uniform scattered component as noted by Vega-Carrillo et al. [17, 18].
Method | Uncertainty budget | uCF (%) | |||||
---|---|---|---|---|---|---|---|
uk (%) | uB (%) | ||||||
Aloka TPS-451C | KSAR1U.06 | Model 12-4 | Source strength | Aloka TPS-451C | KSAR1U.06 | Model 12-4 | |
GFM | 2.27 | 7.00 | 18.41 | 1.45 | 2.69 | 7.14 | 18.47 |
SEM | 1.88 | 6.65 | 14.12 | 1.45 | 2.38 | 6.81 | 14.19 |
RFM | 0.40 | 1.38 | 3.99 | 1.45 | 1.50 | 2.00 | 4.23 |
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4 Conclusion
Calibrations were performed for three types of neutron ambient dose equivalent rate meters, i.e. Aloka TPS-451C, KSAR1U.06, and Model 12-4, using the GFM, SEM and RFM fit methods. The direct component of the neutron ambient dose equivalent rate,
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