Subscribe Now Subscribe Today
Research Article

Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration

Rahim Khabaz and Hashem Miri Hakimabad
Facebook Twitter Digg Reddit Linkedin StumbleUpon E-mail

In present study, the neutron spectra of 241Am-Be measured with Bonner sphere method. The system was equipped with a BF3 thermal detector placed in the center of seven spheres with different diameter (from 8.89 to 30.48 cm). The energy response matrix of the system was calculated by using the Monte Carlo simulation from thermal energy to 18 MeV. The spectrometry system was calibrated, using the shadow cone technique. For this purpose, a new shadow cone was used to prevent direct neutrons of source than to account on the scattered neutrons. Regardless, having a smaller length for new cone, passing the direct neutrons for it was negligible and less than old cone (proposed in ISO). Taking into account the low energy resolution of the BSS system, shape of unfolded spectra from experiment was comparable with the standard ISO 241Am-Be spectrum.

Related Articles in ASCI
Search in Google Scholar
View Citation
Report Citation

  How to cite this article:

Rahim Khabaz and Hashem Miri Hakimabad, 2011. Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration. Journal of Applied Sciences, 11: 2849-2854.

DOI: 10.3923/jas.2011.2849.2854

Received: December 29, 2010; Accepted: May 12, 2011; Published: July 02, 2011


Neutron particles find use in a diverse array of applications in areas of physics, engineering, medicine, nuclear weapons, petroleum exploration, biology, chemistry, nuclear power and other industries (Miri-Hakimabad et al., 2010; Malkawi, 2004; Halim et al., 2005; Ahmed et al., 2006; Adib, et al., 2005). The biological effectiveness of neutrons and neutron-induced secondary particles is so high, thus uncontrolled exposure to free neutrons is hazardous (ICRP, 1996, 2007; Miri-Hakimabad et al., 2009; Basyigit, 2006). On the other hand, the neutron’s quality factor depends on its energy and the response of existing neutron monitors and personal dosimeters is energy-dependent. So, the spectrometric information on the neutron radiation field is very important in radiation protection.

Among the many types of neutron spectrometers that have been developed in many specialized laboratories the world, the system known as multi-sphere, or more commonly as the Bonner Sphere Spectrometer (BSS), is widely used and well recommended by some authors for applications in radiation protection field (Bramblett et al., 1960; Awschalom and Sanna, 1985). BSS consists of a thermal neutron counter embedded in moderator shell (usually polyethylene) and the associated electronics in the case of an active detector like BF3, 3He or scintillators like 6Li (Eu). The BSS is applied to characterize the neutron field from thermal to GeV (Jacobs and van den Bosch, 1980; Liu et al., 1990; Thomas et al., 2002).

The BSS system is very useful since it is simple to operate, portable, has an isotropic response, covers a wild range of energy and the data can be unfolded and interpreted fairly easily (Thomas and Alevra, 2002). Several different types of thermal neutron sensors have been used at the center of BSS. The purpose of this study is to present a study to prepare the BSS based on a long proportional counter filled with BF3 gas.

In this study, the response matrix of energy for BSS with BF3 cylindrical detector has been calculated by Monte Carlo calculations using the computer code MCNP4C (Briesmeister, 2000) because the Monte Carlo method provides a powerful tool for detailed modeling of the process and geometry. One of the methods for calibration of system and determination of scattering contribution is shadow cone technique; in this procedure, a cone places between source and detector to count the scattered neutrons. Because of applying the long BF3 counter, contribution of scattered neutrons was sizable. Thus distance between the neutron source and sphere must be decreased; however, for determination of the scattered neutrons, a new shadow cone should be designed having an appropriate length and a negligible transmission for direct neutrons (ISO 10647, 1996).

This work mainly focuses on providing conditions for measurement of 241Am-Be (α,n) spectrum and discussion of unfolded counting from experiment by BSS in various calibrations. The measurements and calculations were compared then the detail of some different was described.


The Bonner Sphere Spectrometer (BSS) under consideration constitutes of a set of polyethylene spheres of different diameters: 3.5", 4.2", 5", 6.5", 8", 10" and 12". The mean polyethylene density for all spheres of the set was 0.960±0.015 g cm-3. The central thermal detector used is a 2.54 cm diameter 28.20 cm BF3 cylindrical proportional counter (LND2210 type). The BF3 wall was made of copper with 0.89 mm thickness and the effective length of this counter was 25.4 cm and also the pressure of gas filling of BF3, according to the manufacture, was 0.92 atm at 293 K. In this detector, enrichment of 10B was about 96% (Fig. 1). In each sphere a 2.55 cm diameter cylindrical hole was drilled nearly to the center of the sphere.

The response of the BSS was calculated with the MCNP4C Monte Carlo Code, as the number of the 10B (n,α) 7Li reaction within sensitive detector volume per incident neutron fluence normalized to one starting particle. The irradiation geometry is based on a disk source, having the same diameter of the sphere under study, emitting a parallel neutron beam toward the sphere.

The energy response functions for seven detector configurations were calculated for different energies from 10-8 to 18 MeV. The discrete neutron energy values were selected at logarithmic equidistant intervals and at decade boundaries. The calculation of the response was accomplished being selected the tally F4 of MCNP4C, being considered the (n,α) reaction, associated to a card multiplier that contains the volume of the detector, the area of the disk source and the atom density (atom/barn cm) of BF3. For the thermal domain, the S (α, β) treatment was employed in the simulation. The statistical uncertainty was less than 4%. In Fig. 2, the energy responses of BSS system calculated with BF3 long cylindrical proportional counter is shown.

The responses first increase, reach a maximum and then decrease. The reduced response of spheres at low neutron energies is due to capture of thermalized neutrons in the hydrogen of polyethylene. Furthermore, decrease of the response in high energies is due to escape of neutrons from polyethylene sphere. Considering the shape of the response functions, ascertain that the BSS system can be equipped with BF3 long counter and used for neutron spectrometry.


There are many techniques that have been used to evaluate scattering corrections necessary for proper calibration of neutron spectrometer instruments, one of which is shadow cone technique. This technique relies upon the experimental determination of the scattered components, due to both walls reflected and air-scattered neutrons, using a shadow cone designed to prevent any neutrons passing directly from the source to the detector.

Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
Fig. 1: Geometry of structure of BF3 detector simulated in the calculations (all measures are in cm).

Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
Fig. 2: Energy (MeV) response functions of BSS with BF3 long cylindrical counter, as calculated with MCNP4C

The method depends critically on the design of the shadow cone and upon its position relative to the source-detector geometry. One particular design of the shadow cone consists of two parts: a front end, with the length of 20 cm entirely made of iron and a rear section, with the length of 30 cm made of polyethylene (ISO 8529-2, 2000).

Geometry-correction factor for the finite source or detector size in order to tend to unit, generally measurements are made at a distance of more than twice the shadow cone length (ISO 10647, 1996). Therefore, considering the given shadow cone, the minimum distance of source to detector must be 1.0 m.

By using the MCNP4C code, the BSS system consisting of BF3 counter was simulated base on the library (11.5x9.0x4.0 m) with 40 cm concrete walls. In this simulation, the neutron reference spectrum was investigated 241Am-Be source. The spectrum for this source was extracted from the standard ISO 8529-1 (2001). For determining the total count due to direct and scattered neutrons, the 241Am-Be neutron source was considered at the center of room and at 2.10 m height; the separation distance between the neutron source and center of each polyethylene sphere was 1.15 m. The source place was chosen with the goal of minimizing the scattered radiation at the sphere position. For calculating the scattering contribution, the shadow cone (30 cm polyethylene and 20 cm iron) was placed between neutron source and sphere, while distance between the center of sphere and the back face of the cone was 50 cm. The contribution of direct neutrons was given by subtraction of total counts from scattering counts.

In these conditions, the ratio of the scattered neutrons to direct neutrons for small spheres (3.5”, 4.2” and 5”) was more than 2.05, while it is expected to be less than 0.4 (ISO 10647, 1996). Because of using the long counter, a lot of scattered neutrons arrived at counter from a part of BF3 that was out of sphere. To eliminate this problem, external part of the BF3 was covered with 3.0 cm boric acid (H3BO3). The scattered neutrons are prevented to arrive in external part of BF3, due to moderation and absorption in Boric Acid (BA). The ratio of the scattered neutrons to direct neutrons decreased to 1.23. With another calculation, it became clear that less than 4% of neutrons entered to external part of counter; thus it was not necessary to use other layers.

The next stage was decreasing the separation distance between the neutron source and sphere that was limited, because of the length of shadow cone. A new shadow cone was designed with smaller length. It had 35.0 cm length and three parts: a front end, with the length of 17.0 cm constituted by iron; a middle section, with the length of 14.0 cm consisted of solution water with 5% boric acid and a rear section, with the length of 4.0 cm which was made of boric acid entirely. The emitted neutrons from source arrive at iron and they are moderated to lower energy due to inelastic scattering interaction. Then, neutrons enter to water (with 5% boric acid) and some of them are thermalized or absorbed by 1H and 10B. Finally, according to have a high capture cross-section for 10B, thermalized neutrons are absorbed in boric acid. This design was performed to optimize the length, mass and attenuation coefficient of shadow cone. Figure 3 shows the geometrical view of the Bonner Sphere System for counting the scattered neutrons by using shadow cone.

Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
Fig. 3(a-b): Geometry of the irradiation with shadow cone for determination of scattered neutrons: (a) old shadow cone constituted by iron and polyethylene (ISO 8529-2, 2000) and (b) new shadow cone included of iron, solution of water (5%) and Boric Acid (BA)

The attenuation coefficient for a shadow cone is equal to division of detector counts in the presence of the cone to detector counts without cone while the counting must be in free space with no background. Table 1 shows the calculated attenuation coefficient for 241Am-Be neutron source related to each cone, assuming old (50 cm) and new (35 cm) shadow cones. As in the calculation, distance between source and center of sphere with old and new shadow cones were 115 and 75 cm respectively. It can be seen that the new shadow cone has a smaller length but its attenuation coefficient is improved. Using the new shadow cone, separation distance between the 241Am-Be source and center of sphere was considered 75.0 cm. The MCNP calculation revealed that the ratio of the scattered neutrons to direct neutrons in this separation distance, for small spheres (3.5”, 4.2” and 5”) and large spheres (6.5”, 8” 10” and 12”) was less than 0.38 and 0.25, respectively. Table 2 presents the calculated values of the ratio of scattered neutrons to direct neutrons for all spheres in all conditions for using old and new shadow cones.


In experimental measurement by BSS system, seven spheres were positioned along axis of the centre of the source and were exposed separately to fast neutrons from a 5Ci 241Am-Be (50mmx30mm) neutron source for 1000 seconds at a distance of 75.0 cm between the source and the center of spheres.

Table 1: Attenuation coefficient corresponding to each shadow cone for old (50 cm) and new (35 cm) shadow cones
Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration

Table 2: The calculated ratio of scattered neutrons to direct neutrons in various conditions
Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
BA: Boric acid

The BSS was equipped with a cylindrical 2.54 cm (diameter) by 28.2 cm (height) BF3 (96% of 10B). The detector was placed in the center of the laboratory and the source could be moved over a horizontal position at the same height as the detector. In this experiment, distance of detector from beside and behind walls of the room was 4.50 and 5.75 m, respectively.

The separation of the neutron-induced events from pulses due to noise or gamma ray induced events was performed by introducing a discrimination threshold below the lower limit of the neutron induced pulse-height distribution in MCA, whilst rejection of noise pulses did not have too much effect on the neutron sensitivity.

In order to calibration of system, the new designed shadow cone (with 35.0 cm length) was used between the source and sphere. The source-shadow cone distance was 5.0 cm. In these experiments three types of shadow cone with different obscured diameter were applied.

The resulting values from experimental measurement with different detectors for total neutrons (direct plus scattered neutrons), scattered neutrons and direct neutrons are illustrated in Fig. 4. It can be seen that with increasing diameter of spheres, the ratio of the scattered neutrons to direct neutrons (total neutrons minus scattered neutrons) is decreased. Also, for all spheres the ratio of the scattered neutrons to direct neutrons is less than 0.4.

Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
Fig. 4: Experimental measurement determined for different detectors in 1000 sec

The results obtained by the BSS system were unfolded with a modified version of the code SANDII (McElroy et al., 1967). This code uses an iterative perturbation method to obtain a best fit neutron flux spectrum for a given input set of measured detector counts. The procedure consists of a flux spectrum that serves as the initial approximation to a solution.

The direct counts of the 241Am-Be source and energy response functions that have been calculated with MCNP, were used as input values in SANDII. Therefore, in this calculation the neutron spectrum is determined at position of the detector. Also, another experiment with old shadow cone (30 cm polyethylene and 20 cm iron) was done. In this experiment, the separation between 241Am-Be source and center of the sphere was 115 cm and external part of BF3 was covered with 3.0 cm boric acid.

Figure 5 illustrates the experimental neutron spectrum of 241Am-Be source that unfolded with the program SANDII, in comparison with ISO standard spectrum (ISO 8529-1, 2001) using the new shadow cone (35 cm) and old shadow cone (50 cm). As it can be seen a satisfactory agreement has been obtained for the spectrum 241Am-Be source using the new shadow cone, taking into account the low energy resolution of the BSS system. In measurement applying the old shadow cone, spectrum increases in low energies values and spectrum decreases in energies values. Also, the peak of spectrum extravagates to lower energy.

This deviation can be explained by having a great ratio of scattered neutrons to direct neutrons. Diverting the shape of spectrum in low energies happens due to higher excessive increase of this ratio for small spheres and an increase in count error. In general one can conclude that when scattering contribution increases, the spectrum deflects to lower energies.

Image for - Determination of 241Am-Be Spectra using Bonner Sphere Spectrometer by Applying Shadow Cone Technique in Calibration
Fig. 5: Comparison between the experimental neutron spectrums for 241Am-Be, using the new shadow cone (35 cm) and old shadow cone (50 cm)and the ISO standard spectrum


Computational and experimental evaluations of BSS calibration were performed with a 241Am-Be (α,n) source. First, the response function of BSS system equipped with BF3 calculated by Monte Carlo simulation. The general form of response ascertained that this detector can be a proper choice for use in BSS. For calibration of spectrometer, in order to determine the scattered neutrons, the shadow cone method was applied. Because of limitation in reducing of distance between soured and sphere, proposed cone by ISO was unsuitable for this set-up and with use of this cone the ratio of scattered neutrons to direct neutron was greater than standard value. Therefore, a shadow cone with better performance and lower length was used. Then, to decrease the scattered neutrons, the rear part of the BF3 long counter that is out of sphere has been covered with an appropriate thickness of boric acid.

An experimental limited to seven spheres and applying the new shadow cone for calibration has been performed with 241Am-Be source in the library. Although the BSS system has inherently poor energy resolution, the results shown herein indicate a satisfactory agreement. Another experiment revealed that the shape of spectrum would be changed due to increase in scattering contribution. So, by using BSS system equipped to a long detector, base on calibration with new cone, the 241Am- Be spectra can be obtained fairly reasonably.


1:  Adib, M., N. Habib, M. Kilany and M.S. El-Mesiry, 2005. Neutron transmission through crystalline Fe. J. Applied Sci., 5: 5-11.
CrossRef  |  Direct Link  |  

2:  Ahmed, Y.A., I.O.B. Ewa and I.M. Umar, 2006. Variation in nuclear data and its impact on INAA. J. Applied Sci., 6: 1692-1697.
Direct Link  |  

3:  Awschalom, M. and R.S. Sanna, 1985. Applications of bonner sphere detectors in neutron field dosimetry. Radiat. Prot. Dosimetry, 10: 89-101.
Direct Link  |  

4:  Basyigit, C., 2006. The physical and mechanical properties of heavyweight concretes used in radiation shielding. J. Applied Sci., 6: 762-766.
CrossRef  |  Direct Link  |  

5:  Bramblett, R.L., R.I. Ewing and T.W. Bonner, 1960. A new type of neutron spectrometer. Nucl. Instruments Methods, 9: 1-12.
CrossRef  |  

6:  Halim, M.A., S.A. Nessa and M.R. Ullah, 2005. Activation cross sections of 90Zr(n, 2n)89Zr reaction in the neutron energy range 14.10-14.71 MeV. J. Applied Sci., 5: 903-905.
CrossRef  |  Direct Link  |  

7:  ICRP, 1996. Conversion Coefficients for Use in Radiological Protection Against External Radiation. Pergamon Press, Oxford, UK

8:  ICRP., 2007. The 2007 Recommendations of the International Commission on Radiological Protection. Pergamon Press, Oxford, UK

9:  ISO 8529-1, 2001. Reference neutron radiations - Part 1: Characteristic and methods of productions. International Organization for Standardization, 56. CH-1211, Geneva, Switzerland.

10:  ISO 8529-2, 2000. Reference neutron radiations-Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field. International Organization for Standardization, 56. CH-1211, Geneva.

11:  ISO 10647, 1996. Procedure for calibrating and determining the response of neutron-measuring devises used for radiation protection purposes. International Organization for Standardization, 56. CH-1211, Geneva,

12:  Jacobs, G.J.H. and R.L.P. van den Bosch, 1980. Calibration measurements with the multisphere method and neutron spectrum analyses using the SAND-II program. Nucl. Instruments Methods, 175: 483-489.
CrossRef  |  

13:  Liu, J.C., F. Hajnal, C.S. Sims and J. Kuiper, 1990. Neutron spectral measurements at ORNL. Radiat. Prot. Dosimetry, 30: 169-178.
Direct Link  |  

14:  Malkawi, S.R., 2004. Three-dimensional calculations of axial neutron flux distribution in a material test research reactor. J. Applied Sci., 4: 292-296.
CrossRef  |  Direct Link  |  

15:  McElroy, W.N., S. Berg, T. Crockett and R.G. Hawkins, 1967. A computer automated iterative method for neutron flux spectra determination by foil activation. Report AFWL-TR-67-41, Air Force Weapon Laboratory, USA,

16:  Briesmeister, J.F., 2000. MCNPTM-A general monte carlo N-particle transport code. version 4C, Los Alamos National Laboratory Report LA-13709-M, Los Alamos, N. Mex., USA.

17:  Miri-Hakimabad, H., L. Rafat-Motavalli and K. Karimi-Shahri, 2009. Assessment of neutron fluence to organ dose conversion coefficients in the ORNL analytical adult phantom. J. Radiol. Prot., 29: 51-60.
CrossRef  |  

18:  Miri-Hakimabad, H., L. Rafat-Motavalli and K. Karimi-Shahri, 2010. Activation rate uniformity in a bilateral IVNAA facility for two anthropomorphic phantoms. Nucl. Technol. Radiat Prot., 25: 69-77.

19:  Thomas, D.J. and A.V. Alevra, 2002. Bonner sphere spectrometers: A critical review. Nucl. Instruments Meth. A, 476: 12-20.
CrossRef  |  

20:  Thomas, D.J., A.G. Bardell and E. Macaulay, 2002. Characterisation of a gold foil based bonner sphere set and measurements of neutron spectra at a medical accelerator. Nucl. Instruments Methods A, 476: 31-35.
CrossRef  |  

©  2022 Science Alert. All Rights Reserved