AE-24 Transmission of Thermal Neutrons < through Boral F. Åkerhielm AKTIEBOLAGET ATOMENERGI STOCKHOLM • SWEDEN . I960 AE-24 Transmission of Thermal Neutrons through Boral F. Åkerhielm Summary; Transmission measurements have been performed using Maxwellian distributed neutrons from the Rl reactor perpendicularly incident upon a boral absorption plate. American, English, German, Swedish and Swiss samples have been investigated and the results are compared to calculated values. The influence of the absorber grain size is discussed. Completion of manuscript in Aug. 1959 Printed and distributed in June 1960 LIST OF CONTENTS Page Experiments 3 Corrections 4 Sources of Errors 5 Theory 6 The Influence of the Grain Size 8 Results and Discussion 9 References 11 Transmission oi Thermal Neutrons through Boral Experiments The transmission of thermal neutrons through boral plates was measured using neutrons from the Rl reactor. The plates consisted of boron carbide grains embedded in aluminium and the plates were in general clad with aluminium on both sides. Integral measurements *)'were performed using neutrons from a graphite scatterer placed in the inner part of a channel in the thermal column. The neutrons passed through a collimator (30 mm in diameter, 1 m long), the plate to be investigated and a B F« counter (BA type) surrounded by a cover. Both the cover and the collimator were made of boron paraffin clad in aluminium. The cover had a through hole (diameter 50 mm) in line with the collimator. The vertical position of the counter could be adjusted so that it could be placed in maximum intensity. Spectral neutron transmission measurements have been made with the fast chopper at Rl. After having been chopped the neutrons from a heavy water scatterer in the central channel of the reactor passed through the plate. They were then counted by a set of B F~ detectors connected to a 100 channel time analyzer. Both at integral and spectral measurements the transmission was determined as the ratio of the counting rate with absorption plate to that without absorption plate. 'The integral transmission measurements on most of the plates have been made by J. Christensen and Stig Johansson, and they have kindly permitted that their results are published in this report. They also constructed the measuring apparatus. •v* 1 American, English, German, Swedish, and Swiss samples ' have been investigated. Measured transmission values in various regions on these samples are found in Tables la and lb and in Fig. 2. Average values of the transmission through different samples and information about their origin and composition are found in Table 2. The Swedish samples have been denoted by three numbers separated by points according to the following. The first number gives the sheet from which the sample plate is cut, the second number the location of this sample plate in the sheet and the third number the position of the studied region on the sample plate. For the foreign samples the number before the point indicates the sample investigated and the number after the point the location of the studied region on the sample plate. Corrections 1. Correction for the dead-time of the measuring apparatus has been made. This dead-time has been determined by measuring the countingrates with (I) and without (II) a boral sample in front of the counter at two reactor power levels (a and b). Ia/lb (—2) gave the ratio of the neutron fluxes at the two power levels, and the dead-time could then be calculated from Ila/llb. The transmission measurements were made at a power level of 1 kW, at which a counting-rate of about 2500 cps for the unattenuated flux and a dead-time of 15 - 5 |isec were obtained. 2. In order to eliminate the contribution to the counting-rate from the non-Maxwellian flux and the background, the transmission has first been calculated from A- B where A = counting- rate without absorber B - " C= ," D= " with Cd only with boral only with boral and Cd *) Suppliers: Alcoa: Alcoa International Inc., 230 Park Avenue, New York 17, N. Y. USA HDA: High Duty Alloys, Ltd. , Slough, Bucks, England VDM: Vereinigte Deutsche Metallwerke, Frankfurt (Main)-Hedderheim, Germany (Representative: Svensk-Tyska Handels AB, Stockholm 80) Örne: Tekn. lic. Nils Örne, Banérgatan 81, Stockholm Ö, Sweden AIAG: Aluminium-Industrie-A-G, Neuhausen am Rheinfall, Switzerland. 1) IT According to Westcott ' M-?p— = 4* 7- ' v o Cd for a parallel flux and 1 mm Cd. As T = T and R~ , = 320, r is equal to 0. 0062. A correction of t has later o Od been made, which, however, due to the low r-value never exceeded the experimental errors at the measurements. 3. A correction for scattering in the plate has been made. Sources of Errors 1. For certain samples the transmission values are very small (»*10~ ), resulting in lov low counting rates and correspondingly large statistical errors (< 30 %) 2. The Maxwell spectrum incident on the absorption plate has a characteristic temperature higher than 293 K. Due to the fact that the measurements were made using a neutron beam from the thermal column, it is reasonable to assume that this increase is negligible. A t-curve for T = 343 K has, however, been drawn in diagram 1, in order to indicate the temperature influence. 3. Variations exist in the transmission along the surface of the boral plate due to non-uniform distribution of boron carbide grains. For each plate t has been measured at several places and the results (Table 1) show that for all foreign samples and for about half of the Swedish ones t - t r . < 5 % unless the low transmission limits the measuring accuracy. 4. Deviation from parallelism of the flux incident on the plate will cause a decrease in the measured value for t. The boron paraffin collimator inserted in the channel should, however, reduce this deviation to a minimum. 5. Analyses of the boron content per unit area have been performed at the KFAB section. The aluminium in the plates was dissolved byhydrochloric acid and the insoluble part was weighted. The boron content of the grains was then determined and the result was 72. 5 % by weight B and consequently less boron than the formula B,C implies. The weight per unit area is difficult to determine accurately, and the error has been estimated to ^ 5 %. Using the fast chopper at Rl, the dependence of the transmission on neutron energy has been measured. The values for In t are plotted in Fig. 3 as a function of l/v. A straight line has been fitted to these values, and the boron weight per unit area was determined from its slope. The results obtained, agree well with the above mentioned analyses with the exception of the Swiss samples, all of which had a transmission corresponding to a boron weight per unit area of 70 % of that measured by chemical analysis. This is probably due to the fact that the grains during manufacturing were crushed with quartz cylinders. Quartz powder mixed with the boron carbide grains and the boron concentration of the insoluble part was less than that of the boron carbide. Transmission calculations based on these lower boron contents agree well with results from integral transmission measurements. 6. The cross section used for boron is 755 b [ BNL 325 (1958)] . Since the B -content can vary somewhat, especially in boron compounds, there is some uncertainty in the cross section, but this probably does not exceed 1 %. Theory Nomenclature N = total number of neutrons per cm v = neutron velocity in cm/s v T = most probable velocity at temperature T K and 2—^ = absorbtion cross sections of absorber and detector respectively in cm /g at velocity vr 9 d. and d_ = weight per unit area in g/cm detector respectively of absorber and If Maxwellian distributed neutrons are incident normally on a homogeneous l/v-absorber the number of transmitted neutrons per cm and second is 3 - o Introducing X-L/N \ F \ s (x) = n -s e 2 - x/s , - /o ' d s the transmission may be written as 4NvT As the spectrum hardens when passing through a l/v absorber, the effective ifective macroscopic macros cross section decreases with increasing 4, 5) amount of absorber. If a l/v-detector is placed behind the absorber, its counting rate will be proportional to F 33 <SAT dA> " F 3 <SAT ddA + and the follow^ing transmission is measured d (o) - \ (2) A' d n has been calculated to 0. 19 for the BA detector used. 8 For a "black" detector one gets t (E A T d A F , (S ( d ) 3 AA 3 ^^ F 3 (o) •) = (4) and for a thin detector F t (2 d A T 0) = A 22 ^AT A> A T A (5) F , (o) and t (x, o) <; t (x, s D T dD) < t (x, <») (6) The "blacker" the detector is, the larger is the measured ratio of transmitted to incident flux for a given absorber. In Fig. 1 t equals the calculated transmission for a homogeneous layer plotted according to Eq. (3) as a function of d . Curves are drawn A for various detector thioknesses and various characteristic temperatures of the Maxwell spectrum. In Fig. 2 the measured transmissions are compared to those calculated for a BA-counter and T = 293 K. The Influence of the Grain Size If the absorbing material in a sample consists of grains with dimensions - the mean free path in the absorbing material, the trans- mission becomes larger than if the material is distributed homogeneously. ' *) dF ' n — dx ' ' ="Fn-l If the a b s o r b e r grains a r e a s s u m e d to be s p h e r i c a l with a d i a m e t e r of 2R and stochastically distributed, this is equivalent to multiplying the 2) boron content by an efficiency factor e e = a , r, 3 a , 3a / , ~aYI - 1 o ~ In L 1 - —T— + —T— ( 1 - ae - e )J c a 1 a. a V where a = S T , volume of a b s o r b e r grains and a = total volume V T € is drawn as a function of ^Am * — * 2R in F i g . 4 . If in Eq. (7) a—> O an equation is obtained which is in complete a g r e e m e n t with 3) 4) those given in and ' . F r o m (3) and (7) we get t = t[« ( S A T • I l - . 2R, a) • S A T • d A , S D T . d D ] Results and Discussion The computed value for t from (8) is plotted in F i g . 2 with 2R a s a p a r a m e t e r . A comparison between this function and the values obtained experimentally shows that for 2R in (7) a value < 0. 1 m m should be i n s e r t e d for the foreign samples except one. The t r a n s m i s s i o n m e a s u r e m e n t s with the fast chopper (Fig. 3) show that the deviation from a l / v - c r o s s section is negligible even at low v e l o c i t i e s . The chopper m e a s u r e m e n t s also indicate that 2R < 0. 1 m m . At section RMM the boron carbide g r a i n size was d e t e r m i n e d using an eyepiece m i c r o m e t e r . However, the analysis (Table 3) indicates that in s e v e r a l c a s e s the grain size is l a r g e r than 0. 1 m m . F o r 2R in E q . (8) an average value for the grain size should not be used, but a considerably s m a l l e r value ( - l / 3 thereof). Eq. (8) is therefore qualitatively c o r r e c t but quantitatively it has c e r t a i n d i s c r e p a n c i e s , which probably depends on the fact that it only considers one grain size and does not include the (8) 10 effect of small grains assembled between the large ones. On comparison between calculated and measured values in 4), one obtains similar results regarding the calculation of e . Information about the boral samples is, however, incomplete which makes comparison more difficult. The measurements described in this report refer to a parallel flux while those in 4)' refer to neutrons emitted from an infinite uniformally emitting surface. According to Fermi the angular distribution in the latter case is (1 + *J°3 cos 9) d (cos 9) and a t-curve (accor7) ding to ') is drawn for this case in Fig. 1. The foreign manufacturers have evidently succeeded in making the boral sufficiently homogeneous. The effectivity (i.e. the ratio of the boron content, calculated from (3) and the measured transmission, to the measured boron content) of the foreign samples indicated in Fig. 2 is higher than 0. 9 for all samples except the German ones, for which it is 0. 83. This is due to the very large grains (see Table 3). The homogeneity of the Swedish plates is not as good. Micrographs of Swedish 8 9^ and American boral ' ' show that the American plates are much more homogeneous than the Swedish ones. For about half of the Swedish plates the transmission and boron content vary along the surface of the plate and the grain size is large. The relatively large transmission through the Swedish samples is due to the decrease in effectivity caused by the reasons mentioned above. 11 References. 1. WESTCOTT C. H. et al. Effective Cross Sections and Cadmium Ratios for the Neutron Spectra of Thermal Reactors Gen. Conf. 1958 P/202 2. PERSSON R. and ÅKERHIELM F . Transmission of thermal neutrons through boral AEF-76 (1956) (internal report) 3. LAFORE P. and MILLOT J. P. Determination de la reduction d'efficacite du bore ou d'un autre absorbeur employe sous forme de poudre disséminé dans une produit non absorbant, en fonction de la grosseur des grains. CEA 675 (1957) 4. BURRUS W. B. How Channeling between Chunks Raises Neutron Transmission through Boral. Nucleonics Jan. 1958 5. BEAUGE R. Determination de 1'efficacité d'un écran de boral et mesure de la quantité de bore contenue dans cet écran. Service de la Pile de Chatillon (1957) 6. ZAHN C. T. and LAPORTE OTTO Absorption Coefficients for Thermal Neutrons. Phys. Rev. 52_67-74 (1937) 7. von DARDEL G. The Interaction of Neutrons with Matter Studied with a Pulsed Neutron Source. Trans. Roy. Inst. Technol., Sweden,75 (1954) 8. HRU UR No. 21:57 (internal communication) 9. HRU UR No. 36:57 (Internal communication) 12 Table 1 a. Measured Transmission of Swedish Samples No. Transmission % Table 1 b. Measured Transmission of Foreign Samples Sample Country- Transmission % Designation England Switzerland USA GermanyTable 2. Sample Country and ,, r 4. Manufacturer ,, , Mark Boron Content mg B/cm 2 a) c) Total Thickness mm t exp Tiomogeneous % % ' Obtained by proportioning to the plate thickness a) computed from, data given by the manufacturer b) according to chemical analysis c) according to chopper measurements t,nom is calculated from Eq. to the i (3) v / with T = 293 °K and d.A equal ^ value underlined in the table. 13 Table 3. Measurements of the Boron Carbide Grain Size (Performed at RMM) Sample Designation Average Grain Size in u Max. Grain Size in |i Min. Grain Size in |x Remarks 1) approximately equal amounts of 2 grain sizes 25 J|L and 75 - 125 2) small amount of 25 \x grain size 3) plus a very small portion of sizes between 10 - 25 J|L 4) very uniform grain size 5) a very small portion of 5 \i size 6) rather uniform grain size When not stated otherwise, the major portion of the powder is of average grain size. * * * * * parallel flux Flux having a distribution 100 Fig. I. Calculated transmission through boron (Maxwell distributed flux) 300 mgB/cm Legend Alcoa HDA • AIA6 s Örne V VDM X • -1 10 Grain diameters A B C D 0 mm 0.1 0.2 0.3 -2 10 10 10 100 200 mg B/cm Fig. 2. Measured transmission values compared to calculated values, assuming that the incident flux is Maxwell distributed T = 293 °K and S D T dD = 0. 19 (BA detector). Parameter = grain size 8 00 9 msec 10 T ravel-time 2100 Vel. Fig. 3. Transmission measurements on samples H2, A and Wl using the fast chopper at Rl (for absorber H2 calculations have been made on the influence of the grain size) 1.0 0,5 0.2 0,5 10 Fig. 4. The efficiency (e) for the absorbing material versus the product of macroscopic cross section and grain size (2 for different volume ratios (a). . — • 2R.) LIST OF AVAILABLE AE-REPORTS Additional copies available at the library of AB ATOMENERGI Stockholm - Sweden Printed In Price AB N o Title 1 Calculation of the geometric buckling for reactors of various shapes. N. C. Sjöstrand 1958 23 3 2 The variation of the reactivity with the number, diameter and length of the control rods in a heavy water natural uranium reactor. H. 1958 24 3 3 Comparison of filter papers and an electrostatic precipitator for measurements on radioactive aerosols. R. Wiener 1958 4 4 3 Author McCnnck Pages ja Sw. er. 4 A slowing-down problem. I. Carlvik, B. Persbagtn 1958 14 5 Absolute measurements with a 4n-counter. (2nd rev. ed) Kerstin Martinsson 1958 20 4 6 Monte Carlo calculations of neutron rhermalization in a heterogeneous system T 1959 13 4 6 Metallurgical viewpoints on the brittleness of beryllium. G. Lagerberg 1960 14 4 9 Swedish research on aluminium reactor technology. B. Forsen 1960 13 4 10 Equipment for thermal neutron flux measurements in Reactor R2. E. Johansson, T. Nilsson, S. Claesson 1960 9 6 N. G. Sjöstrand J. S. Stor, 1960 34 4 N G Sjöstrand, J. Mednis, T. Nilsson 1959 12 4 M m Högberg 11 Cross sections and neutron yields for U* , U and Pu"* at 2200 m/sec 12 Geometric buckling measurements using the pulsed neutron source method 13 Absorption and flux density measurements in an iron plug in R l . R. Nilsson, J. Brann 1958 24 4 14 GARLIC, a shielding program for GAromi Radiation from Line- and Cylinder-sources. M. Roos 1959 36 4 15 On the spherical harmonic expansion neutron angular distribution function S. Depken 1959 53 4 of the 16 The Dancoff correction in various geometries. 1. Carlvik, B* Pershagen 1959 23 4 17 Radioactive nuclides formed by irradiation of the natural elements with thermal neutrons. K Ekberg 1959 29 4 18 The resonance integral of gold. K. Jirlow, E. Johansson 1959 19 4 19 Sources of gamma radiation in a reactor core M. Roos 1959 21 4 20 Optimisation of gas-cooled reactors with the aid of mathematical computers. P. H. Margen 1959 33 4 21 The fast fission effect in a cylindrical fuel element. I. Carlvik, B. Pershagen 1959 25 4 22 The temperature coefficient of the resonance integral for uranium metal and oxide. P. Blomberg, E. Hellstrand, S. Hbrner 1960 25 4 23 Definition of the diffusion constant in one-group theory. N. G. Sjöstrand 1960 3 4 25 A study of some temperature effects on the phonons in aluminium by use of cold neutrons. K-E. Larsson, U Dahlborg, S Holmryd 1960 32 4 26 The effect of a diagonal control rod in a cylindrical reactor. T. Nilsson, N. G. Siostrand 1960 4 4 23 RESEARCH ADMINISTRATION: A selected and annotated bibliography of recent literature- E. Rhenman, S. Svensson 1960 49 t 29 Some general requirements for irradiation experi- H P. Myers, R. 1960 9 6 30 Metallographic Study of the Isothermal Transformation of Beta Phase in Zircaloy-2. G. Östberg 1960 47 6 32 Structure investigations of some beryllium materials. 1. Fäldt, G. Lagerberg 1960 15 6 33 A-n Emergency Dosimeter for Neutrons. J. Braun, R. Nilsson 1960 32 6 Skjoldtbrand Affärtlryck, Stockholm I960
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