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����������Investigation of Heat Effect on the Shielding Properties of Some Local Concretes  

W. A. Kansouh 
Reactor Physics Department, Reactors Division, Nuclear Research Centre, Atomic Energy Authority, Cairo, Egypt
E-Mail:kansouh2573@gmail.com

ABSTRACT

The effect of heat on gamma ray and neutron shielding properties of  two types of the local concretes ( basalt concrete; (=2.2 g/cm3 and magnetite concrete; (=3.9 g/cm3) with two different water to cement ratios for both were investigated. The samples were exposed to temperatures between 20 to 300 oC and 800 oC.
Small losses in attenuation coefficients for gamma rays and neutrons were observed for the studied types of concretes. Investigations have been performed using  a narrow beam of Cs-137 source and a collimated beam from ET-RR-1 reactor. A gamma spectrometer with NaI(Tl) detector and a neutron-gamma spectrometer with stilbene scintillator were used during measurements. 
The results show that the magnetite concrete has the best attenuation coefficients for both gamma rays and neutrons (an effective shield) and the best resistance for high temperature effects and fireproof than basalt concrete. 
    
Key Words : Magnetite Concrete / Basalt Concrete / Heated Samples / Attenuation 
                             Coefficient and  Removal Cross Section.

INTRODUCTION

Concrete is specified in building and civil engineering projects for several reasons, sometimes cost; sometimes speed of construction or architectural appearance, but one of concrete's major inherent benefits is its performance in fire, which may be overlooked in the race to consider all the factors affecting design decisions. Concrete is said to have a high degree of fire resistance and, in the majority of applications, concrete can be described as virtually 'fireproof'. This excellent performance is due in the main to concrete's constituent materials (i.e. cement and aggregates) which, when chemically combined within concrete, form a material that is essentially inert and, importantly for fire safety design, has a relatively poor thermal conductivity. It is this slow rate of heat transfer (conductivity) that enables concrete to act as an effective fire shield not only between adjacent spaces, but also to protect itself from fire damage. The use of concrete in nuclear facilities for containment and shielding of radiation and radioactive materials has made its performance crucial for the safe operation of the facility(1).  
Long-term degradation of concrete structures under permanently humid environmental conditions is mainly influenced by interacting chemical and mechanical processes leading to the destruction of the microstructure by the dissolution of cement constituents and the propagation of micro-cracks. Mechanical damage accelerates the chemical degradation as a consequence of improving transport properties(2). Early reported research results, for example, were unable to distinguish between damage caused by heat and damage caused by radiation(1).

Since the year 2000, there have been many reports published about the deterioration of concrete(3-8). Some of these have reported the results of experimental work, and others have proposed models that might be used to predict the deterioration of concrete over periods of time. Many of the predictive models have focused on the micro-scale processes. Few of these have addressed the effects of radiation on the concrete.
 Tests on the effects of long-term exposure to elevated temperatures showed that the compressive strength in general tended to decrease with increasing temperature and with the length of exposure. Temperature affects the modulus of elasticity(9). The moisture content in the concrete near a hot surface decreases because of pressure-induced flow(10). Heating of refractory concrete cause physical and chemical changes mainly because of removal of water. The compressive strength is reduced after exposure to about 540 oC(11). In conventional concrete, long-term exposure to high temperatures can cause changes in compressive strength, modulus of elasticity, creep resistance, conductivity, diffusivity, and shrinkage/expansion characteristics. General speaking, the threshold of degradation in the concrete is approximately 95 oC(11). In some investigations, radiation led to an increase in temperature of the concrete up to 250 oC. Such a temperature increase may cause considerable damage to the concrete even if there is no radiation effect(12,13). The effect  of  temperature is even more pronounced on the tensile strength of concrete. A temperature increase from 20 to 100 oC may cause a reduction of tensile strength of concrete by as much as 50%.   
In the present work a comparative study of the heating effect on the attenuation coefficients for fast neutrons and gamma rays distributions through basalt concrete and that of magnetite concrete having different values of water to cement ratios.. These concretes were made from local materials in Egypt. Investigations were performed using different sources of radiation and two types of spectrometers. The obtained results results show that this magnetite concrete is better than the basalt concrete under investigation in their attenuation coefficients at different temperatures for gamma rays and fast neutrons.  The results were put in tables and figures to get a conclusion from the discussion.  

EXPERIMENTAL METHODS

 1. Materials and sample preparation 

The basalt and magnetite concrete shields were made using local materials with densities 2.2 and 3.9 g/cm3  and with different water to cement ratios. Basalt concrete  has the values of water to cement ratios equal to 0.35 and 0.4 and magnetite concrete has the values of water to cement ratios equal to 0.28 and 0.35. The elemental composition of concrete depends mainly on the mix proportions and the chemical composition of the materials used. Mix proportions by weight of basalt and magnetite concretes are given in Table 1. The choice of relative percentage ingredients, compressive strength, tensile strength and flexural strength to obtain the mentioned suitable density for basalt and magnetite concretes was done by the Structural Engineering Department, Faculty of Engineering, Cairo University, Cairo, Egypt. Chemical composition as a percentage by weight of the different constituents in the basalt and magnetite ores used in the two mentioned concretes are presented in table 2. 
   
 Table 1. Mix proportions by weight of two types of concretes

Raw materialBasalt Concrete
(=2.2 g/cm3Magnetite Concrete
(=3.9 g/cm3Portland cement11Sand1.23.33Basalt2.4-----Magnetite-----7.53Water0.400.28 Plasticiser           0.02410.006Silica fume0.100.10 

 





Table 2. Chemical composition as a percentage by weight for basalt and magnetite ores   

ConstituentsBasalt oreMagnetite oreSiO249.214.5Al2O315.42.8CaO9.22.3FeO7.8----MgO5.43.1Fe2O35.172Na2O3.7---TiO22.6----K2O0.9---P2O50.4----MnO0.08----S----0.02P----0.3Mn----0.26
	For radiation test, special specimens of 10 cm x 10 cm x 10 cm were prepared to measure the attenuation coefficient of different types of concrete to gamma ray penetration from Cs137 point source and also the attenuation coefficient to reactor beam penetration ( fast  neutron and total gamma rays (primary and secondary)) to investigate the heat effect on the shielding properties of  the investigated concrete.

2. Test procedures

2.1 Heating exposure technique
	
A big furnace chamber was used. The samples were placed unloaded in the cooled furnace chamber and the temperature was increased to reach certain degrees (100, 200, 300, 800 oC). After an exact period (2h), the furnace switched off until cooling, then the samples were tested.

2.2 Radiation test

2.2.1 Cesium-137 gamma ray source test
	
Shielding tests of gamma rays were performed using cesium-137 point source of 3.7x104 Bq (1 �Ci) activity. Tests were carried out on four different samples of concrete (two samples of basalt concrete and two samples of magnetite concrete) using 4 in. in diameter of NaI (sodium iodide crystal) detector connected to a computerized Multichannel Analyzer (MCA)(14). The different samples of each type of concrete heated to different temperatures (100, 200, 300 oC) were subjected to Cs137 point source for 1000 seconds to investigate the shielding properties against gamma radiation. The relation between temperature and attenuation coefficients was concluded. The attenuation coefficient was calculated from the following equation:

� = 1/10[ln Io/I)]

where I is the intensity of gamma rays after the shield material, Io is the intensity of gamma rays before the shield material and � is the attenuation coefficient factor.

2.2.2 Reactor beam test

Attenuation properties of fast neutrons and total gamma rays for basalt concrete  (w/c=0.4) and magnetite concrete ( w/c=0.28) and heated to 300 and 800 oC)  have been examined. Tests were carried out by measuring the transmitted fast neutron and gamma ray spectra through different samples of concrete barriers. Concrete barriers of cubic shape of 10 cm x 10 cm x 10 cm were used to perform the experimental measurements.
            Measurements have been carried out for the four types of concrete using a reactor collimated beam (18 mm dia. and 58.5 cm length) of neutrons and gamma rays. The collimated beam is emitted from the horizontal channel number 2 of the (2MW) research reactor ET-RR-1. Special beam filters and collimators were used to provide a beam of specific intensity and geometry suits the measuring purposes. In addition, a special detector collimator and filter were used to eliminate the side scattered radiation and to reduce the thermal neutrons to enhance the discrimination capability of the discriminating techniques. Experimental arrangement layout was shown elsewhere(15,16) .  The neutron-gamma spectrometer with stilbene scintillator (4 x 4 cm) and fast photomultiplier tube were used to measure the proton and electron pulses amplitude distributions. The undesired pulses of recoil proton and electron due to neutrons and gamma  rays were achieved using the pulse shape discrimination technique (PSD) based on the zero-cross over method. Spectrometer setup and the description of the discrimination technique were given elsewhere(17,18). Spectrometer linearity, discrimination capabilities and energy scaling were tested and checked before the course of experimental measurements by measuring the spectra of gamma rays emitted from 22Na, 137Cs, as well as, from Pu-�-Be neutron source. The diagram of the measuring system was shown elsewhere(16,19). The measured pulse amplitude distributions of recoil protons and electrons were converted to energy spectra of fast neutrons and gamma rays using two unfolding codes (N Spec and G Spec) based on double differentiation and matrix correction methods respectively(20,21). A ZnS (Ag) scintillator was used to check the reactor power fluctuations during the course of the experimental measurements.

RESULTS AND DISCUSSION

1. Variation of Cs-137 gamma ray attenuation coefficient against temperature

	Table 3 and Figure 1 show the variation in gamma ray attenuation coefficient ( �, cm-1)  for Cs-137 source against temperature changes for the four types of concrete. At 300 oC the attenuation coefficient for all studied mixtures lost between 9 and 10% of their initial values at 25 oC. Magnetite concrete with water to cement ratio equals 0.28 has shown the best attenuation coefficient and has the best resistance to heat (Figure 1). It is clear from Table 3 that the magnetite concrete and the lower water to cement ratios for the two kinds of concrete, generally show the best attenuation coefficient and has the best resistance to heat.   

Table 3: Variation of gamma radiation ( Cs-137) attenuation coefficients ( �, cm-1) 
               for some local concretes against temperature

Temperature oCMagnetite concrete (w/c=0.28)Magnetite 
concrete 
(w/c=0.35)Basalt
concrete 
(w/c=0.35)Basalt
concrete 
(w/c=0.40)250.24290.23100.20930.20751000.23970.23200.21200.20102000.23620.21880.20520.19723000.22020.20900.19170.1878                         
Linear attenuation coefficients ((, cm-1), mass attenuation coefficients (� /�, cm2/g), relaxation length (�, cm), half value thicknesses (HVT, cm) and tenth value thicknesses (TVT, cm) of gamma rays for these concretes have been achieved from the attenuation relations and are given in Table 4.

Table 4: Radiation shielding parameters of gamma rays for concretes under 
               investigation  

Concrete type(, 
cm-1(/�, 
cm2/g �, 
cmHVT, 
cmTVT, 
cmMagnetite concrete
(w/c=0.28)0.24290.06234.11692.85309.4813Magnetite Concrete
(w/c=0.35)0.23100.05924.3290.3.00009.9697Basalt concrete
(w/c=0.35)0.20930.09514.77783.311011.0033Basalt concrete
(w/c=0.40)0.20750.09434.81933.339811.0988
2. Reactor total gamma ray attenuation index

For the region of reactor total gamma rays energy from 1.262 to 7.197 MeV  Table 5 and Figure 2 show variation of reactor total gamma attenuation coefficient ( �, cm-1)  against temperature changes (300 oC and 800 oC) for basalt concrete (w/c=0.40) and magnetite concrete (w/c=0.28).  At 300 oC the linear attenuation coefficient is nearly the same as that at room temperature for basalt concrete mixture. But for magnetite concrete mixture at 300 oC it lost nearly 2% of its initial value at room temperature. At 800 oC for basalt and magnetite concrete mixtures linear attenuation coefficients lost 7% of its initial values at room temperature. It is clear from Table 7 that  the magnetite concrete mixture has shown the best attenuation coefficient for reactor total gamma ray and has the best resistance to heat. 

Table 5: Variation of reactor total gamma attenuation coefficient ( �, cm-1) for two different 
               types of concrete against temperature
   
Concrete Type25 oC300 oC800 oCMagnetite concrete(w/c=0.28)0.10260.10090.0954Basalt concrete(w/c=0.40)0.08520.08610.0793 
               
It is clear from Tables 3 and 5 that the attenuation coefficients of gamma rays of (Cs-137) point source for two types of concrete (magnetite concrete with w/c =0.28 and basalt concrete with w/c=0.40) are more than that for reactor total gamma rays for the same types of concrete. This can be attributed to the fact that reactor total gamma rays consisted of primary gamma rays from the reactor and secondary gamma rays resulted from the interactions of neutrons with the samples which decrease the values of the attenuation coefficients. But gamma rays from Cs-137 point source are primary gamma rays only. Total attenuation coefficients ((, cm-1), total mass attenuation coefficients (� /�, cm2/g), relaxation length (�, cm), half value thicknesses (HVT, cm) and tenth value thicknesses (TVT, cm) of gamma rays for these concretes have been achieved from the attenuation relations of the integral fluxes and are given in Table 6.

Table 6: Radiation shielding parameters of reactor total gamma rays for concretes under 
               investigation  

Concrete type(, cm-1(/�, cm2/g �, cmHVT, cmTVT, cmMagnetite concrete (w/c=0.28)0.10260.02639.74666.754422.4464Basalt concrete (w/c=0.40)0.08520.038711.7371.8.133827.0305
Table 6 shows that the attenuation properties of total gamma rays for magnetite concrete are better than that for basalt concrete. 

3. Reactor fast neutron beam attenuation index
 
For the region of neutron energies from 1.2-13.6 MeV  Table 7 and Figure 3 show the variation of reactor fast neutron removal cross section against temperature changes (300 oC and 800 oC) for basalt concrete (w/c=0.40) and magnetite concrete (w/c=0.28).  At 300 oC the reactor fast  neutron removal cross section lost nearly 3.5% of its initial value at room temperature (25 oC) for the two mixtures of concretes. At 800 oC for both concrete mixtures the reactor fast neutron removal cross sections lost nearly 17.5% of its initial values at room temperature (25 oC). This can be attributed to the fact that both concretes had lost more of their water content. It is clear from Table 7 that the magnetite concrete mixture shows the best attenuation coefficient for fast neutrons and has the best resistance  to heat. 


Table 7: Variation of reactor fast neutron removal cross section (�R, cm-1) for two 
              different types of concrete against temperature

Concrete Type25 oC300 oC800 oCMagnetite concrete (w/c=0.28)0.16540.15950.1364Basalt concrete (w/c=0.40)0.16200.15630.1336           
    
              Removal �R (En) cross sections, relaxation lengths (�), half value thicknesses (HVT) and tenth value thicknesses (TVT) of fast neutrons for these concretes have been achieved from the attenuation relations and are given in Table 8. 

Table 8: Radiation shielding parameters of fast neutrons for concretes under 
               investigation

Concrete type�R, cm-1� (cm)HVT(cm)TVT(cm)Magnetite concrete (w/c=0.28)0.16546.04594.189813.9238Basalt concrete (w/c=0.40)0.16206.17284.277814.2160
Magnetite concrete has clearly little more better attenuation properties for fast neutrons than basalt concrete.  

CONCLUSION

From this comparative study for the heating effect on some types of locally prepared concretes with different water to cement ratios, it can be concluded that:
1- Magnetite concrete with its different water to cement ratios under investigation has attenuation 
     properties for gamma rays, total gamma rays (primary and secondary) and fast neutrons better than 
     basalt concrete under investigation.
2- Magnetite concrete has the best resistant properties to heat than basalt concrete.
3- Concrete with lower water to cement ratio has the best attenuation properties for radiation and the 
     best resistant properties to heat.
4- Concrete has some benefits of using it :
     -It has a slow rate of heat transfer (making it an effective fire-proof shield).
     -Skillful mix design further refines concrete's inherent performance.
     -Concretes has been given the highest possible material classification for its fire resistance.    
5- Produced results for heat effect on different types of concrete may be useful for nuclear 
     research community and shielding designers.

Acknowldgement

The Auther would like to thank Prof. R.M. Megahid, Reactor Physics Department, Reactors Division, Nuclear Research Center, Atomic Energy Authority, Cairo, Egypt for his valuable discussion and  H. M. Hassanien, Structural Engineering Department, Faculty of Engineering, Cairo University, Cairo, Egypt, for the preparation of the different types of concrete under investigation. 

REFERENCES

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3. Mahdy M, Speare P, Abdel-Raheem A, (2002) Egypt of Transient High Temperature on Heavy 
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7. Yousef S, AlNassar M, Naoom B, Alhajali S, Kharite M (2008) Heat Effect on the Shielding  and 
    Strength Properties of Some Local ConAGPQRSTc����������<	�����Ⱥ�����zoz�aVK@Kh�DhlH%CJaJh�Dh�n�CJaJh�DhO@CJaJh�DhO@5�CJ\�aJh�Dh@�CJaJh�Dh�d�CJaJh�Dh�6�CJ]�aJh�Dh@�6�CJ]�aJh�Dh@�5�CJ\�aJh�DhUrCJaJh�DhUr5�CJ\�aJh�DhZ�5�CJ\�aJh�Dh`3q5�CJ\�aJh�Dh�n�5�CJ\�aJh�Dh�4�5�CJ\�aJSTc�����3
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