ML20010G717
| ML20010G717 | |
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|---|---|
| Site: | Clinton  |
| Issue date: | 06/01/1977 |
| From: | Mollon L AFFILIATION NOT ASSIGNED |
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| 554, NUDOCS 8109220448 | |
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,,- t hh Brooks &Peikins. Incorporated Report 554 r
i l Prepared by:
- Leslie Mollon -
i Director - Nuclear Product i Development 4 Brooks & Perkins. Inc. l 12633 Inkster Road i Livonia, MI 48150 , i 1 i 1 , I June 1, 1977 l I l l ) l ! i l, Brooks &- De rki'- .;. I Spent Fue Stc , Module Corr >s. ;r. i Report j i i l l l i 4 1 4 i 4 l 3109220448 810914 PDR ADOCK 05000461 i A f_E
$h Brooks &Perkins.Incorpomted.
ABSTRACT Brooks & Perkins, Inc. Spent Fuel Storage Module Corrosion Report No. 554 A determination is made from published data of the expected life of a storage module following a rupture in the water barrier cove ring. The environmental conditions external and internal to the module are defined. The various types of corrosion which can occur are also defined and their experimentally determined corrosion rates are listed. Results show an expected life to be at least greater than fifty three (53) years and prob?bly greater than sixty (60) years following the occurrence of the rupture to . the water barrier covering.
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- 2 Report 554 h Brooks &Perkins, Incorporated BROOKS & PERKINS, INC. SPENT FUEL STORAGE MODULE CORROSION REPORT PURPOSE: The pr.rpose of this report is to dete/u ine from published data the extent of any deterioration that is likely to occur over a forty year period to tha shielding capability of a Brooks & Perkins, Inc. spent fuel storage module following a water leak in the stainless steel covering.
_ BACKGROUND: The spent fuel storage module (SFSM) is a slender sqmre-shaped tube with open ends that is used for the storing and the shielding of one spent fuel assembly in a light water nuclear reactor storage pool. The tube is constructed with the inside and outside coverings being made of type 304 stainle ss steel. These two stainless steel surfaces are welded tc,gether at the top and bottom of the tube over an inner layer of a thermal neutron shielding material called BORALtm,
.A group of SFSM's are assembled into a tightly packed array called a high-density storage rack. A network of horizontal and diagonal members separate the modules within the rack and provide the necessary lateral support. The racks stand in a vertical position on the bottom of a forty foot deep storage pool.
The water in the storage pools is constantly circulated through a series of filters which causes a constant water flow within the pool. J The water is monitored and controlled for pH and temperature within specific limits depending on the type of nuclear reactor. l The quality of the water in the storage pool of the two types of reactors ! is controlled within the following ranges: Preasurized Water Reactor (PWR) l water type demine ralized l i wa.ter temperature 70 to 1500 F (21 to 66 C) pH at 77 F (25 C) 4. O to 8. 0
- boron, ppm 1800 to 2200 chloride ion, ppm, max. O.1
* -(4. 5 to 10. 6 at Combustion Engineering Reactors)
Report 554
-h Brooks & Perkins. Incorporated fluoride ion, ppm, max. O. I total suspended solids, ppm, max. 1. O solids filtration, microns, max. 25 Boiling Water Reactor (3WR) water type demineralized water temperature 70 to 150 F (21 to 66 C)
L. . pH at 77 F (25 C) 5. 8 to 7. 5 chloride ion, ppm, max O. S total heavy element, ppm, 1 max. O. I total suspended solids, ppm, max. 1. 0 , solids filtration, microns, max. 25 The thermal neut:-oa absorbing material BORAL " is a 9andwich type panel that has outer surfaces of type 1100 aluminum and a core of boron carbide uniformly dispersed in a matrix of type 1100 aluminum. DISCUSSION: The shielding capability of a BORAL panel is due to its ability to capture thermal neutrons. The capture of thermal neutrons is accomplishcd by the B10 (boron-ten) isotopes that aic contained within the boron carbide particles. These boron carbide particles are chemically inert (unreactive), heat resistant, highly crystalline an ' nearly equivalent to diamond in hardness. In order for corrosion to cause a reduction in the shielding capability of a BORAL panel, the boror. arbide particles have to be physically displaced from the pand. A displacement of the boron carbide particles to occur would require the following sequence of events. s ,w _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ - _ _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ - - _ _ _
,' Report 554 B'aoks & Perkinz Incorporated (1) the complete removal of the outer protective aluminum surfaces on the BORAL panel.
(2) the complete removal of the aluminum matrix surrounding each boron carbide particit.. (3) the physical displacement of the boron carbide particles. It in resting to note that BORAL has been used in fuel storage pools l since 1964 and samples have been subjected to many corrosion studies [3] [4] for long periods of time. In none of these exposures has it i been reported that any boron carbide parti :es we te displaced. The progression of corrosion to the outer surface is directly dependent upon the area in contact with the water. The outer surface will reduce in thickness at the same rate in mils per year as the edge will be attacked if the entire panel is in contact with the water. If only the edges of the B( RAL , are exposed to the water, the corrosion rate would be the same but a rr.ach longer period of time would be required for the total failure of the panel to occur. In order to effectively enrapolate from previous test results, it is often necessary to make reasonable interpolations or projecuons from the pub- . lished data because of differences between test and actual conditions. It must also be kept in mind that most, if not all, tests are conducted with constant or precisely controlled conditions throughout the test period which would not be the case in an actus11eak. ' ( Alwitt et a1 [5] states, " Aluminum reacts readily with water to form a hydrcus oxide film. Depending upon the conditions of film formation, the film is more or less protective against subsequent corrosion. Growth occurs in two states: a pseudoboehmite film is produced initially and then is covered l with a layer of bayerite crystals. By analogy with the aging mechanism in a i celloidal suspension, it is thought that the pseudoboehmite dissolves and re-precipitates as bayerite crystals. The growth of bayerite is inhibited at higher temperatures (800-100 C), presumably because the pseudoboehmite is better crystalized and dissolves more slowly."
"The growth kinetics and properties of the pseudoboehmite film produced at 100 C have been studied extensively. Less is known about the layers pro-duced at low temperatures, but Hart has reported the weight gain and electron diffraction analyses for aluminum samples immersed in water at tempera-tures between 20 and 80 0C. "
There are at least four significant changes that will occur immediately to the water that enters into the internal voids in the storage module. Those changes are as follows: I'.eport 554
$-h Brooks &Perkins, Incorporated
- 1. Flow Rate. The pool water surrounding the storage module is constartly flowing and therefore its chemistry, purity and temperature can be con-trolled within precise limits. The 17ater entering through a hole into the internal voids of the storage module will cease flowing and will become stagnant once the voids are filled. The internal water will change from the external water and will be the corrodent media to consider for the long term affects of corrosion. As pointed out by Godard, [6] " Movement of the corrosive liquid usually accelerates the rate of corrosion. "
- 2. Shift in pH. The internal water will react with the aluminum up.>n contact and cause the pH to change. The pH will increase or decreasF towards a eteady pH near neutral depending on whether the initial cond8. ion is acidic or alkaline. This change in pH is reported by the following:
, A. Sedriks et al "The change of pH with time for initially acidic solutions (i. e. , pH < 2) in the p e sence of dissolving aluminum is shown in Figures 1 and 2 (The curves shown could be reproduced within t 0. 05 of a pH unit. ) In general, the change can '>e characterized by 'd (1) an initial increase in pH, and (2) the subsequent attainment of a ste&dy pH value. " (c) 7c73, EFFECT OF INITIAL D'4 5 - a , 9
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, , . . I 0 S 25 60 1 5 V WWW TIME (min) E (mid FIGURE 1 - The change of pH with time as a fune. tion of (a) FIGURE 2 - The change of pH with time as a function of (al initial pH of solution, ib) presence of aluminum ions, and (c) elloy content, and (b) liquid / solid ratio.
effect of oavgen.
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$h Brooks &Perkins, Incorporated "The steady pH value is related to the concentration of aluminum .
ions in solution. . . . and is associated with the onset of precipitation of aluminum hydroxide, AL (OH)3 " B. "Peterson et al E83 report that in sea water (pH 8. 2) the corrodent in crevices in Type 304 stainless steel was less than 2(pH). The pH at the growing front of exfoliation crevices in aluminum alloys does not appear to have been reported, but it is postulated to be acid, having a pH of possibly as low as 3.2 based upon meaaurements of pH at the tips of stress corrosion cracks in aluminum alloys." C. B. F. Brown. [9 3 "The acidity is caused by hydrolysis of one or more components of the metal or alloy, and the acidity persists because of the restricted interchange between the corrosion cell and the bulk environment. " _ D. Peterson et al " Figures 3 and 4 show that regardless of the initial potential and pH, the crevices on stainless steel polarized the pH shifted in the alkaline direction to the domain where water is unstable and hydrogen discharge would be expected. One would therefore expect that cathodic protection has been achieved, since the potential of the surface has been shifted into a region where stainless steel is known to be cathclically protected. In addition, the pH has shifted to a value vhich indicates that the solution within the crevice is benign to stainless steel. " p y ..-. - _ -
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sa FIGUAE 3 - Typ. so4 staine st ste.,s. cre .e. potatination ricone 4 - Typ. so4 Staini.ss si. . c, ic. poia,,natio. and pH data at various distanc.s from the crevice openeng and pH data at various distances from th, tite,ece openeng and at various times. Shown on a partial Pourbasu diagram, and at various temas. Shown on a partsal Po.ad..'is diagram. The 0.6 M Nacl solution had an inetsal pH of 7.6 The 0.6 M Nacl sciution had are inities pH of 1.9. 4
Report 554
$h Brooks &Perkins.Incorpormed E. B &P Report No. 553 11 Samples of the SFSM were placed in water baths having a pH of
- 4. 5 and 10. 5. Within a few hours the pH of the water that entered the SFSM had changed and was steady at 7.1 and 7. 7 respectively.
- 3. Oxycen Content. The content of dissolved oxygen in the internal water will be depleted by the oxidation of the metal surfaces. The decelerating effect on th peactivity of the solution by this de-aeration can be seen in Figure 1(c) J. The de-aerated solution required 38% more time to change pH from 1.0 to 3.0 and 80% more time to change from 1.0 to 4.0 than the solu-tion containing dissolved oxygen. This delay in reaction time is also caused by the development of a protective oxide film on the surface of the alumi-1.um which tends to arrest further corrosion action.
- 4. Ion Concentration. The volume of the internal water will be small com-pared to the surface area of the metal faces and will therefore become saturated with ions very quickly. The further ionization of the aluminum surfaces can proceed only to the extent that aluminum ions precipitate out of solution in the form of an insoluble compound. A study of a potential-pH diagram (Po b ix) for the aluminum-water system (see Figures 5 and 6 of MacDonald 2 et al) discloses the following reaction will occur within a pH range of 3 to 8. 5 and a temperature range of 770 to 1400F.
2 Al + 6 H2O -) A13033H O 2 4 + 6H+ + 6 electrons A diseolved aluminum atom will react directly with water to form the precipitate gibbsite and bayerite (A193 2 3H2O). T-@
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(a) refers to the p!ir ci a 10-*m 011 solution. Fsc. 6 Potential-pH diagrm fair the aluminium.uater system at WC. (4 refers to the pile of a id'm Oli solutioes. The precipitate is a hydrated oxide of aluminum which is stable up to 135 C (275 F). The entrapped water will become saturated by the forming of the gibbsite ant. cayerite, and therefore would be a self-limiting influence to - the corro sion. CORROSION DATA BORAL
- 1. One year test results water type BWR pH 5. 6 to 7. 7 t emp. 68 to 78 F (20 to 26 C) corrosion rate, mpy 0.28 expected life (at 15 mils thickness)* > 53 years
*10 Mils of Clad Plus 5 Mils of Matrix Holding Boundary Layers of B C.4 w.= _ _ . _ _ - - - _ - - - - - - - - - _ - - - - - . - - - - . - - - - - - - - - - _ - - - - - - - - - - - -
,' Report 554 L U Brooks & Perkins. Incorporated
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- 2. 2000 hour test results b4) water type BWR pH 7. 0 temp. 1900F (880C) corrosion rate, mpy 1. 2 to 2.1 estimated corrosion rate
@ 700 to 1500F. , mpy .18 to . 32 expected life (at 15 mils thickne s s)* 745 years
- 3. Twelve years of service [Il water type PWR boron nil pH 4. 0 to 8. 0 (est. )
temp. 70 to 150 F (21 to 66 0C) (est. ) . co rrosion rate, mpy nil expected life (at 15 mils i thicknes s)* > 60 years STAINLESS STEEL - tyoe 304
- 1. General Corrosion (13]
water type BWR or PWR pH ! 7. 0 to 11 temp. 5720F (3000C) oxygeri, ppm ( . 01 to 2 chlorides, ppm (.I corrosion rate, mpy (2 estimated corrosion rate
@ 150 F, mpy (.6 expected life (at 60 mils thicknes s) p 60 years
- 10 mils of Clad plus 5 mils of Matrix Holding Boundary Layers of B4C.
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Repcit 554 [hh Brooks & Perkins. Incorporated
- 2. General Corrosion after 3000 hours EI4l water type high purity, demineralized hydrazine, ppm . 01 to . 07 oxygen, ppm ( .005 chlorine, ppm ( .05 pH 6. 95 to 9. 58 flow ra.e. gal /hr. 3. 5 temp. 320 F (160 C) corrosion rate, mpy ,01 expected life (at 60 mils thickness) > 60 years
- 3. Stress-Corrosion-Cracking after 3000 hours EI4l water quality same as 2 above stress % of . 2% yield 120 re sults " Meta 11ographic examination of selected samples also failed to reveal any cracking. "
expected life (at 60 mils thickness) > 60 years ALUMINUM - tvoe 1100F
- 1. General Corrosion after 14,200 hours I water type high purity, demineralized oxygen, ppm 4 to 5 pH 5. 0 to 6. 0 flow rate, fps 7. 6 te mp. 1940 to 356 F (90 to 180 C) corrosion rate, mpy 0.16 expected life (at 15 mils thickness) > 60 years L . ... o-
Report 554 Wh Brooks &Perkins, Incorporated STAINLESS STEEL (type 304) coupled with ALUMINUM f tvue 1100F)
- 1. Crevice and Galvanic Corrosion (15]
water type high , -ity, demineralized oxygen, ppm 4 to 5 pH 5. O to 6. O flow rate, fpm O. 5 te mp. 194 to 356 F (90 to 180 C) time, hrs. 1100 1775 2000 Al max. pit depth, mils 2 <3 <5 Al corrosion rate, mpy 0 '. 0.1 0.1 S.S. Corrosion rate, mpy 0 0 0 expected life (at 15 mils > 60 yrs >60 yrs >60 yrs thickness of A1) CONCLUSION: A thorough review of the published test data indicates the materiale used in the Brooks and Perkins Inc. spent fuel storage module (namely 304 Stainless Steel and 1100F Aluminum) provide adequate corrosion , resistance to achieve a life expectancy of forty years without a reduction of neutron absorbing capability when used in a BWR or PWR storage pool with a rupture in the stainless steel covering. - -__ _ __ __ o - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
Report 554 hh Brooks &Perkins, Incorporated _
REFERENCES:
[ 1] Yankee-Rowe, Fuel Storage Rack, Part No. YM-H-1-2, Aug,1964 [ 2] Dai, riand Pov>er Cooperative, Lacrosse Plant, BWR, Mar,1975 [ 3] BLP Report No. 551, Corrosion Resistance of Boral to 1 Yr. Exposure to BWR Pool, Feb, 77 [ 4] L. Marti-Balaguer and W. R. Smalley, " Evaluation of Control Rod Materials: CVTR Project", CVNA - 86. Carolinas-Virginia Nuclear Power As sociate s, Inc. (1960) [ 5] R. . S. Alwitt & L. C. Archibald, Some Observations on the Hydrous Oxide Film on Aluminum Immersed in Warm Water, Corrosion Science, Vol. 13, pg. 687 i [ 6] , H. P. Godard, The Corrosion Behavior of Aluminum, NACE-Corrosion,
, Vol. 11, Dec. 19 55, pg. 55
[ 7] A. J. Sedriks, J. A. S. Green and D. L. Novak. On the Chemistry of the Solution at Tips of Stress Corrosion Cracks in Al Alloys. NACE-Corrosion, Vol. 37, No. 5, May 71, pg.199 [ 8] M. H. Peterson, T. J. Lennox, Jr. , and R. E. Groover, A Study of Crevice Corrosion in Type 304 Stainless Steel, Proceedings of 25th NACE Conference, 314-317, National Asscciation of Corrosion Enginee-rs, Houston (1970). Quotation from [9]. [ 9] B. F. Brown. Concept of the Occluded Corrosion Cell. NA CE - Co rro sion, Vol. 26, No. 8, ~Aug. 70, pg. 249 [10] M. H. Peterson and T. J. Lennox, Jr. A Study of Cathodic Polarization and pH Changes in Metal Crevices NACE-Corrosion, Vol. 29, No.10, get. [11] B&P Report No. 553, pH Shift of Water Inside Spent Fuel Storage Module, Feb. , 77. [12] D. D. MacDonald and P. Butler, The Thermodynamics of the Aluminum-W ter System at Elevated Temperatures. Corrosion Science 1973, Vol.13, pg. 265 [13] Ndional Assoc. of Corrosion Engineers, Corrosion DG Survey,1974, pp. 34 & 252 n
Report 554
- hh Brooks &Perkins, Incorporated
[14] A. P. Larrick, Corrosion Studies in Simulated N-Reactor Secondary Syst;3m Water Encironment. Atomic Energy Comntission Research
- and Development, Report HW-76358, Hanford Atomic Products Operation, May 1963, pg. 7,10 & 22.
4 [15] J. L. English and J. C. Griess, ~ Dynamic Corroiton for the High - Flux Isotope Reactor, ORNL - TM - 1030, September, 1966, pg. 1, 2, 3, 4, 23, 26, 27, 31 l I }J 4 1 4 i oo _ _ _ _ _ , _ _ _ _ , . _ , , , , , _ _ _ _ _ __ , _ _ _ _ _ _ _ _ , _ _ , _ _ - _ _ _ , , _ _ _ _ _ , _ _ , , _ , _ _ __
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as \ n .:,, m p . . f J [bW;B %4j[id PN DENSITY S S Spent fuel storage expansion of on site and central stort.Ye pools are most cost effective with maximum g densification of fuel elements.The p d key to this concept is the Brooks & Perkins's Spend Fuel Storage Module which incorporates Brooks & Perkins' Scral S -the most widely used neutron absorber for fuct storage applications, as well as for a wide range of other applications.
@ Featuring Boral* neutron absorbing / shielding materiai and spent fuel storage modules.
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C5' 2 75*U M5' 2 75*N Ea:, a r 50 e2:n rocrc cry cre so';amma a/0 '2 Ye A r-an eas i 1 me: 3. e a .c e e P.e ;rzes- Ef annar ca ,,, p . um 5 CX ran ea e:> Amm 500p m a ) Byen Cartee 39e-414 L,e, a ca tce '.m, sn e : r: e :s a 5,/eV ;a a ra, and ea.es a res cae of 'N ana:9,e naas 5::A s a ctw m c2:e a constn; cf to: :at a e.e sr : !!MCH ANIC AL STR EN GTHS O F BORAL PAN ELS (Min. 35%i a sec v. 9 a rar < f a tram rc cac <.a a s wm As use:" 1 ,,e ; :-T,: ca-C: ress : . Sre gr- 1 SMC FLe Stran Y c;es ne;re s re cen *e; tyre carra : 52
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;re s; a:e s: a :re s ce rz :e:,.m aec ress rnac,- : =n- Th 77 2 45 2 45 sc i Tr 177 v* -
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i '" 'gt' 'j'* ter t TO. 2 Fe reu';n a e9 a n enra:: ens 05 re:essr, 'T tre l sMc:'c a= 2C- S 7 C ;e:'n s!a cr:sZesc:= As :20Jcnesa : vse n r - m a' j p^ 'q*' 7ts/.rr SFr-et *,~m n s r r:wn c. ecses c' 177 a C12m: 255e C15ir es Trese g3;cnc:,em a re r . x< f:r cre:re ce: .e3 T,na.noressesa sn.ra e- 3, ,77 u33 3 377 y use m s e-* '.e: s' rage mcca ea cr c:rer a:D 'atc s re 7n 255 153: in 255 553 Tens e Sper;m-re:c F eva: ci engn-Ya. Be : ng v: ment ns/m cf *c"O Unas/m at wcm p ev. B': ( o'ntent gace Th 177 114, Tn 177 - 05 Overall Panel Thickness per urit area 7_ nM '1;3 in 263 145 I Or.ches) , I Nimeters) (Grams /sq cm ) Femet E'enga:co m ?") l Yo 4.s c EList::ty
# 50
- I C75 t 91 010 --
CSS 2 16 -020 Th 177 70 Th 177 5 8x10t i Th 'E5 45 in 265 4 4 s 10' : 110 2 79 030 . Stear Svengn Wa'er A: sorption 142 3 61 040 ) m cr.cnc'* Jn) (%) 178 4 52 C50 (24 ers g (5 res # 215 5 46 060 g.W 2200 :s0 Th 177 1142 'h 1770 G5 0 429 M 265 1356 Th lE51940 0 E20 l Ees ces ce m re manufa:'c e cf spe-t '.e! strage rnoc; es Bora: Pas g::r meeir': ma's r Bra' care s c rcerrq a: Dor.a pacuct pedocance a's: Men use: cure m er se:Zrs cf rea:tr st e cs.snu cce., cc-r:r r:cs c::e:m:ai eva re ma o assu acce r cc-int us )
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.<'< N O Spent Fuel Storage Modules ,
T a JN ' l gD patented T'
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Brooks & Perkins' Spent Fuel Storage Modules consist of concentre inner and ou er square "shroucs" which integra3y encapsutate Boral reutron ._
; I-absorber plates...atso providtng the required structurat charactcnstes for g
[ Fina!. ssemblyand fo use in sDent fLel storage racks. I , 'j f The manufactuang process, develooed by Brooks & Perkins, utilizes the t of the module utili:esthe , l ! most modern adaptaten of hydros, zing technoiogy in the nuclear industry , i most modern adaptatior' ~,i The fLxture. designed by B&P is over 25 fct long and we.ghs over 30 tons. It 4: f., c w uses extreme prsst res to form the mod.ia components into a high precision l' g yr & rKins. sandwich type struture. ' j Tre Boral neutron absorber plates are encapsulated withm tne inner and cuter shrouds with the ends of the snrouds formed togemei. . s interface is l
. then weided af each ec. Te structural design is further enhanced by the i
i forming of convex stat'ening beads on the sides of the module. V{ . Rigid inspecten is performed en ~ ., each finished rnocule, subsecuent te 80RAINEUTRJN AR%RBER7. - . - , the qua!Ity Controis implemented dur- " ing the producton procedure, to see lNN that Vanations do not exceed Ine allow- I *l l at,'a inleances for the entire length. . .
! Modules are a!so selected at random ,35 Theinnerand outer shroudsi the module are welded int l ,
?-
and subjected to vanous types of NDE testing. as specified, to assure the adequacy of the We!ds and structure. , a-$ ] u tube configurations on Brooks & Perkins-designet d ' OUTER g l; All inspecton follows the schedules and procedures as presenbet by e.
} M ,M ,e " .y
? a tud na seam e er oenetration weld is 100f hSu Brooks & Perkins QuaLy Assurance
.- d visually inspected and per CCNVEI ' ** ,
** odically examined by NCl Program.
J ~ 0 i i HIGH DENSITY SPINT FUEL STORAGE RACKS USING BROOKS & PERKINS' SPENT FUEL.MRAGE MODULES PERMIT.. W l l increased Storage Ca pacity. The Borai neutren ab.,rber in tne modu!e perm <s T
\
[ j J closer siacing of spent fuel f 9ments withsi a rack. High Strengin and Rigidity. Sandwich construction of the rnodu'e of'ers the [' ~ '. Eachmoduleisfullyinsoecte
. O following tne procedures pr h$ hest strenc*n-to-weight rato avaltable. f - .
~ '
kiple Desigt.and Fabrication. The sandwith structure module can be readily ; ~
- scribed by Brooks & Perkir-i
/
g rigid Quality Assurance Pr designed to meet the ?ructural and shielding requirements at each storage 3- - gram, site and cN De easily and quickfy assembled into a "ack rth a m:ntmum of welding. "^ Low Co';ts. Manufactunng costs are reduced as a result cf the eBcient form- " ' U i '#J.J* 'P ' ing of the macules and s:mplified rack assembly of the high precision com- ~ " y .9 . [ f r%g[- $ ' p, ponents. , I # k j I__-e, L h 4 i' Spent Fuel Storage Module Specifications
'1 ^ L- 'I 7 I -
Type 304 Stainless Steet ." ~~.} ,, Shroud Matertats-Type 6061 Atummum
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(Cnoice of) t ; Type 5083 Aluminum , l l Cors Materia!- Boral , a g p8-
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j Dimensions-Lengn: 120 to 192 in13048.0 to 4876.8 mm. 47 ,E Q c'J f; a ' ,*
.030 to .060 in30.52 mm. vg inner Shroud:
Outer Shroud: .030 to .110 in32.54 mm. M. l <
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Boral Thickness: .075 to .215 in11.91 to 5.4S mm. O insice Dimension: insice Corner Radius: Stiffening Bead 5.5 to 10.5 in11391 to 266 7 rnm. Typ. 25 in16.35 mm.
) m
##['
f Prc:rusen: Tyo. 125 in1118 mm. / End Configurations- Straight Reinforced s flared Cacoed >_
.- I BRO 0KS & PERKINSprovides a complete
- fabricetion/ consultation service forproducing
- EDRAL" components...
I 6 f Fabricating Boral plate into neutron shielding components requires special knowledge as to its properties and ex-l perience in working with this composite material. Brooks & Perkins has developed unique capabilities in working with Boral fabrication problems and offers a complete service to Boral customers. These include welding, cutting, shearing, punching, drilling, sawing, forming and countersinking. Illustrated here are a few of the Boral components pro-duced by Brooks & Perkins or Brooks & Perkins customers. Whatever your needs, this expertise and experience is avall-able to you. Call orwrite, outlining yourspecific requirements.
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l . , ;;, !W ' w 3 e j t i _ , This % thick Bora> plate was completely i cut by plasma arc method, both on outer I edges and the circular hole. ,, , ,
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*]f..p7, Boral components. .
A typical spent fuel storage pool with storage racks featu.ing Boral panel construction. You can te!! the leader by the facilities it serves: Zion 1 + 2 Yellow Creek 1 t-2 Dresden 2 + 3 Susquehanna 1 + 2 Hartsville 1 + 2 Cook 1 + 2 Sequoyah 1 + 2 Duane Arnold 1 Peachbottom 2 + 3 Phipps Bend 1 + 2 Maine Yankee Belefonte 1 + 2 Cooper Browns Ferry 1,2 +3 Hatch 1 + 2 Salem 1 + 2 Pilgrim 1 Fitzpatrick Vermont Yankee Limerick 1 + 2 Yankee Rowe Perry 1 + 2 Monticello Lacrosse Plus overseas facilities c= Brooks & Perkins U.s,.0,, ice: ee-ean otrice: 8 BROOKS AND PERKINS,INC. BROWNLINE LIMITED INCORPORATED Naciear eroducts aroup Tamian way,creen Lane Hounsic v, Middlesex 12633 Inkster Road Livonia. Michigar A3150 U.S.A. TW4 6BL, England Tel.:(313) 522 2000 Tel.:015724321
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L tecnnical nuisetin
' NOVEMBER,1975 f qD ,. ~.
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Neutron Shielding Material
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l BORAL PLATE SHIELDS NEUTRONS , WITHOUT INCLUDING GAMMA RADIATION Boral shielding material offers the unique ability to abs)rb only a soft gamma ray (0.42MeV) and an easily absorbed thermal neutrons without producing ha'rd gamma radi- alpha particle are emitted. l I ation. A dispersion of boron carbide,in aluminum that is Boral offers excellent neutron shielding capabilities for clad in 1100 aluminum sheets, Boral is a sandwich mate- a wide range of applications. It is being used extensively rial produced in standard sizes up to 48 x 120 , ang as a shield in spent fuel storage racks. It has also been in standard mill thicknesses of .177, ( .012) and .265 used on inner section of reactor shields, shutdown con-l ( .015). trol rods, as neutron curtains and shutters for thermal colun:ns. In addition, it has been fabricated into housings These sizes a,re in stock for immediate delivery. Other to shield sensitive electronic and avionic equipment and as
- sizes up to168 in length can be specifiedsubjectio special shipping and storage containers for radioactive materials.
inquiry. Boral plate is also available in several forms including: Boral absorbs slow neutrons with a minimum of secondary Stainless Steel Clad / Encapsulated . . . and with alumi-radiation being induced. With each neutron absorbed, num edge cladding / sealing.
- Patent applied for.
SHIELDING CONSIDERATIONS FOR THE THERMAL NEUTRON R:dioactive materials produced by the nuclear industry today create a variety of radiation, including alpha par-ticles, beta particles, gamma rays, neutrinos and neutrons. Alpha and beta particles are earily shielded by relatively thin sheets of metals. Neutrinos, althot;gh highly pene- _ _ _ _ _ trating, appear to have !.'ttia physiological import ince. Only _ g pamma rays and neutrons require special shielding con-s'ideration, with appreciable thi,,kness of shielding mate- " % =surnons- -- - j rills to provide radiatica protection. Gamma radiation is ~ c* -- \ most effectively absorbed by high-density materials such as 7 -
~'-
Ind, steel and co.icrete. The best elements for neutron attenuation are boron, hydrogc.1, lithium, along with vvater end polyethylene. Most shielding mdorials will readily absorb neutrons, but in doing so they ir 'e secondary gamma rays in the 5 to p. , N - 10 MeV range. This, . ' turn, requires further shielding NsM$, 1NG
- and heat dissipJ.on. Boron is unique in its ability to shield s tha thermal neu.ron without leaving any significant residual N radioactivity. Each attenuated neutron produces only one N soft gamma ray (0.42 MeV) and an easily absorbed alpha pirticle in the process. By contrast, cadmium dieldMg \ . A'N\K cmits a 6 MeV gamma ray and leaves a reddue of tour r:dioactive isotopes. s Boron is available in several forms: crystalline, amorphous and boron carbide. Boron carbide offers the least expen-sivs form 9 highly concentrated boron. It is extremely hard, atomically dense, light weight, chemically inert, with a high melting point and high compressive strength. .
Properties and Characteristics of BORAL The boron carbida in the core of the sandwich panel is evenly Boron Carbide dispersed throughout a matrix of aluminurrs The outer clad- ttype 2. ASTM ding or " skins" of the sandwich panel is Mumsum. BORAlm C750-73T) 97.00% min. - Total boron and carbon panels are identi fied by the nominal thickness of the total 77.00% max. - boron ~ sandwich panel and the minimum percentage content of 70.00% min. - boron boron carbide in the core. 3.00% mar. - boron oxide 2.00% max. - iron 19.75 % 3 .3 % isotope B5 Chemical Composition Corrosion Resistance Aluminum BORAlm offers the same excellent corrosion resista*.ce as (1100 Alloy) 99.00% min. - aluminum 1100 alloy aluminum. It provides unlimited service in boric 1.00% max. - silicon and iron acid solutions when the pH is controlled between 0 and 8.5.
.05 .20% max. - copper Corrosive attack to the aluminum cladd.ng will occur in strong
.05% max.- manganese alkaline solutions (pH 9.5) and at a temperature near boiling
.10% max. - zine (212*F). For unlimited service in these environments, we
.1P% max. - others recommend capsulating the BORALm in s'ainless steel
.05% max. - others each sheathing.
Physical Properties of Base Materie.ls Density (gm/cc) Coefficient Of Thermal Expansion Aluminum 2.71 (per *F) Boron Carbide 2.51 Aluminum 13.1 x 104 (68-212' F) Core (35% B.C) 2.64 Boron Carbide 2.5 x 104 (68-1400' F) Malting Temperature Range Specific Heat ('F) (cal /gm/*C) Atuminum 1190 to 1215 Aluminum 0.23 Boron Carbide 4440 Boron , arbide 12.36 Therrnal Conduct:vity . (cal /cm2/cm/*C/sec) Aluminum (77* F) 0.53 Boron Carbide (77' F) 0.065
Mech:nical Prcpertins cf Bcsa Mat: rials Modulus of Elasticity (tension) Percent Elongation (in 2*) (psi) (75' F) (,,,/ Aluminum 10 x 10* Aluminum 35 Boron Carbide 64 x 106 Boron Carbide N/A Tensile Strength - Ultimate Shear Strength (psi @ 75* F) (psi @ 75' F) Aluminum 13,000 (annealed) Aluminum 9,r00 (annealed) Boron Carbide N/A Boron Carbide N/A Tensile S'rength - Yield Compression Strength (psi @ 75' F) (psi @ 75' F) Aluminum 5 000 (anneated) Aluminum 5,000 (annealed) Boron Carbide N/A Boron Carbide 398 - 414,000 Mechanical Strengths Of BORAL Panels (Min.35% B.C Core) Weight-Typhal Compression Strength - Compression Failure (Ibs/sq. f t.) . (lbs/ inch of width) Th. .177 2.46 2.45 Th. .177 1140 Th. .265 3.67 3.65 Th. .265 2140 Tensite Strength - Ultimate Compression Strength - Buckling Failure (Ibs/ inch of width) (Ibs/ inch of width) 7 a. .177 1230 Th. .177 300 Th. .265 1530 Th. .265 560 Tensil' Strength - Yief d Flexural Strength - Max. Bending Moment (in-lbs/ inch of width)
~(1bs/ inch of width)
Th. .177 1140 Th. .177 95 [.',e} (, Th. .265 1510 Th. .265 145 Percent Elongation (in 2*) Modulus of Elasticity (75' F) Th. .177 5.8 x 10* Th. .177 7.0 Th. .265 4.4 x 105 Th. .265 4.5 Water Absorption Shear Strength (Ibs/ inch of width) (24 hrs @ 0 psi) (5 mins. @ 2200 psi)
- l Th. .177 1142 Th. .177 0.295 0.429
- l Th. .265 1386 Th. .265 1.940 0.620 l Shielding Properties of BORAL Panels (Min.35% B.C Core)'
Neutron Transmission Factor Removal Cross Section (Theoretical) (Theoretical) Th. .177 1.74 x 10-' Th. .177 14.0 IN-' Th. .265 2.30 x 10-3 Th. .265 21.6 IN-8 Neutron Transmission Factor Removal Cross Section (Experimental) (Experimental) min. nom. min. nom. Th. .177 3.5 x 10-8 1.7 x 10 2 Th. .177 20.4 IN-' 23.2 IN ' Th. .265 11.5 x 10-8 5.5 x 10 Th. .265 26.0 IN-' 31.4 IN ' Heat Generation From Neutron - Alpha Reaction 7.4 x 10 watts /sq. ft. x unit thermal neutron flux. O)
\~, " Corrosion of Aluminum Alloys in an Aqueous Solution of Boric Acid and Sodium Hydroxide."
" Boron Carbide Production Properties, Application."
Dr. Alfred Lipp; Reprint from "Technische Rundschau" Dr. E. H. Hollingsworth; Aluminum Company of America Nos.14, 28, 33 (1965) and 7 (1966).
"A Handbook on Baron Carbide and Elemental Boron." The data presented in this bulletin is, to the best of our Norton Company knowledge, correct and up-to-date based on the above
" Aluminum Standards and Data." The Aluminum Association references and our own independent laboratory tests. .
Fabricating with BORAL Plata
- in fabricating Boral plate, it is recommended that forming g% 'f ,
operations be limited because of the nature of the sandwich *
< j material of the plate. Generally, a %" plate may be formed at ,
.f g,,
90' right ingles providing a %" radius is held. In forming # _ _' f, , jf - cylinders, z%" to 8' OD sizes may be made with tolerances 4, p >' of =M*; over 8" the tolerance is =%". When forming small M* 9/,f. _,,
-f ,,
diameters, the sheet must be annealed during forming to ., f,' ,, prevent parting of the sandwich. / e4 2 #,a ?- e eh.; * *
~
Welding of Boral plate is not recommended if mhdmum ,. , strength ,s i re;utred. In most applications, are welding is done .
.7 to butt pistes together when widthe over 48' are needed, or when speual clips au required. For the tyst welds, clean the clad surfaces with a fine wire brush, then butt all joints gs tight as possible. For large arev., pre-heat Boral plate to Borat plate can be welded by the heliarc process, as 400*F. in an oven or on a hotplate; a torch should not be shown in these fabricated samples. Care should be used. The welding are must be held as close as possible to used to butt weld joints as close as possib!a.
the Doral plate, use Amperage settings for welders must be determined by trial. Other recommendations in fabrication of Boral plate. l Drilling - Use carbide tip drills, slow speeds, high feed pres- ; sures. Drilling is recommended only when holes cannot bo - t punched. Countersinking - Use 4-flute carbide tip type at low speeds, high feed pressures. \ Punching - Use carbide tip punch and die of hardened tool ', , steel. Punch and die must be kept sharp to maintain hole ',l ' % 4_. e 7 f-OC g sizes to tolerances of 2.005* ?' .s - C-i d?li , Sawing - Use a 10 to 14-tooth blade, cutting at 75 feet per minute. If c 111-inch blade is used, allow 24" per blade for MEENNND P ? : -W NM " 9
%" Boral and 36* for %" Boral plate. Tolerance for saw i ;.[J"gf*? C~O ^ ~' ~^
cuts is e.J15 : g.s . Shearing - Boral can be sheared on 8-foot-length tolerances of &". Sharpen shear blades frequently. This %" thick Boral plate was ccmpletely cut by Plasma arc cutting - Boral plate can be cut to special shapes plasma are method, both on outer edges and circular or sizes by plasma arc. hole in the center. BROOKS & PERKINS A. ww. - .. w ' '"
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Provides A Complete Fi . M
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Fabrication Service - f -a .
= A '
For BORAL Components Fabricating Boral plate into neutron 9[W p$ w ;p ""'*"". g- Q 4 1 1 shielding components requires special ...
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knowledge as to its properties and ex-perience in working with this compos- , h>$gf'M..adNMMMM.yh'*e !. . _
.j ]
ite material. Brooks & Perkins has de- yThis- Boral-lined .neutronoshieldingy This 14 foot high spent ftel cell tm veloped unique capabilities in working y-Jacket was produc,:ed by welding Boral - age rack war built by Brooks & % i with Boral fabrication problems and geomponegat. Brooks &, pep ( kins of Boral and Aluminum. l
-t ,
offers a complete service to Boral - - - - - - - - - - - - - - - customers. - - - - ~ - - - ~ - - - - - - - - - - - - - - - - - j I litustrated here are a few of the Boral components produced by Brooks & l Perkins. Whatever your needs, this ex-
- . , ~
s pertise and experience can be of I \
/ [d' benefit to y your specif,ou. Call or write, outlining ic requ:rements.
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p- .
^#,s-Cesigned by Nu: lear ,
Designed by NUS services Corp, i Two different configurations of Boral and aluminum spent fuel storage racks (sample sections) for BWR fuel assemblies, q
+y Brooks NUCLEAR PRODUCTS
&PerkinsInc.
12633 Inkster Road . Livonia. Michigan 48150 (313) E22-2000 Fabrir ntinn Cyt ??4 Anrni Panale Cvt 9G
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