ML20246N074

Applicant Exhibit A-4,consisting of Technical Rept 748-30-1, Boraflex Neutron Shielding Matl Product Performance Data,

ML20246N074
Person / Time
Site:	Saint Lucie
Issue date:	01/24/1989
From:	James Anderson BRAND INDUSTRIAL SERVICES, INC. (BISCO)
To:
References
OLA-A-004, OLA-A-4, NUDOCS 8903270295
Download: ML20246N074 (21)

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REPORT 748-30 -1 BORAFLEX

. NEUTRON SHIELDING MATERIAL Product Performance Data August 25, 1979

( .

Prepared by:

J. S. Anderson Technical Director -

Brand Industrial Services, Inc.

s,, Aug. 25, 1979 ,

e o

e *e en a b ip i . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _

. Report 748-30 -1

' - - 'Aug. 25, 1979

• ~Paga 1 of 14, ,

( BORAFLEX NEUTRON SHIELDING MATERIAL ,

Product Performance Data

~

BISCO REPORT 748-30-1 GENERAL Boraflex neutron shielding material is a precisely controlled, borated .composite designed to effectively attenuate thermal

. neutrons while maintaining functional stab'ility in complex and '

long-term environments.

Boraflex is comprised of a polymeric silicone encapsulant en-training and fixing fine particl,es of boron carbide in a homogeneous, stable satrix. The inherent stability of both silicones and carbides results in compatibility with a variety of chemical environments concurrent with strong ionizing radiation.

The physical characteristics of Boraflex allows fabrication and handling in continuous pieces, with the damage resistance of elastomeric.

Boraflex is manufactured and Quality Assurance controlled to a safety related nuclear criteria consistant with 10CFR50, appendix B, and is included in NRC licensed fuel storage racks as well in use for general shielding applications. Dimensional capabilities of the f .

s manufactured product are consistant with most engineered design requirements and assured minimum B10 loadings varying up to a limit of 0. 036 grams B 107 ,,2/0.100" of thickness are available.

e

Report 748-30 -1 Aug. !25, 1979 P::ga 2 of 14 .

SILICONE POLYMER CHARACTERISTICS

. (.

l Boraflex is comprised in part of a methylated polysiloxane elastomer performing as the matrix element of the composite shield.

i The polymer is non-revertable and halogen free (less than 10 ppm I total leachable halogens) and exhibits elongation in excess of 100% at maximum tensile strengths in excess of 300 psi.

The temperature stability'of the polymer is illustrated in )

"able I showing the effects of heat aging at'177 C (350 F) or the hardness (shcre A) of the elastomer over a 6000 hour0.0694 days <br />1.667 hours <br />0.00992 weeks <br />0.00228 months <br /> period.  ;

i 4

Table I

( -

an 'c ca.'ra

% i

. I S.

L .

5 *

g. f __________ ____ __________

- ,i

. 48 e

l

, n 16

( un un . no. ... . .. no TREAFAL A4tasC (as00RS)

Report 748-30 -1 i Aug. 25, 1979 Pcga 3 cf 14 .- .

The polymer is fire retardant, with anALOI of 43 and an ASTM E-84

(

surface flame spread rating of 5,and passes a Mil-1-16923 Thermal ,

Shock Test.

\

The effect of various chemical exposures on the polymer is shown

~

in Table II.

i Table 'II Chemical Effects on Polymer q chemical Duration / Temperature ' Volume ChangoV l Wat'er 7 days /100'C nil j 1

• St'eam

• 14 days /20 psi +5% j Hydrochloric Acid (10%) 7 days /24 C nil Phosphoric Acid (10%) 7 days /24 C nil

. Ammonium Hydroxide (sat.) 7 days /24 C nil t

l In each case where a volume change is noted, the polymer returns to the original measured volume within 2 days after removal from the chemical soak.

BORON CARBIDE CHARACTERISTICS Boraflex contains a fine boron carbide powder in varying amounts depending on specification requirements. The boron carbide powder meets all the requirements of ASTM C-750-74 nuclear grade II material and may, by specification requirement, meet the nuclear grade I criteria. Specifically, the requirements listed in Table III and Table IV apply.

~

-Aug.

- 25, 1979 8

Paco 4 ef 14 I l .

' Table III i

-( Chemical Requirements of Boron Carbide Powder Total Boron 70.Q weight 4 minimum ,

10 B content of Boron 18.05 weight t minimum B0

• 23 3.0 weight 4 maximum e Iron 2.0 weight 4 maximum .

Total Boron plus carbon 97.0 weight 4 minimum f

Particle density 2.40 grams /cc minimum i

l l

. i Table IV Particle size distribution  ;

sieve Designation _ Typical 4 left on Sieve

( 120 2% ,

325 604 In addition, the weight loss of the boron carbide powder, when heated to 200 C,for one hour in an inert atmosphere is less than 200 ppm.

(

w

. . . . .4. . ... . . . . . . . .

- - - _ - - _ _ _ _ - _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

m2 port t e s-J u .- A Aug. ' 23, 1979 Ppg 3 5 of 14 ,

i BORAFLEX PHYSICAL PROPERTIES

'(

Although specific physical properties of Boraflex are affected by boron content, those properties are significantly represented by a standard composition of 0.020 grams of B Oje,2 in a thickness of 0.100". Table V lists the elemental composition of Boraflex consistant with that standard condition.

Table V Boraflex Elemental Composition (0.020 gra B 10 ,,2 7 at 0.100" thick)

Boron 31.5 weight t .

carbori 19.0

• Silicone "

24.5 -

oxygen 22.0

• Hydrogen f3.0

• Neutron transmission measurements of Boraflex have been made at'various 10 i B loadings and are shown in Table VI, equalized to 0.100" thickness.

The measurements were made at the University of Michigan, Ford Nuclear Reactor, and in each case at neutron -

energies of 0.06 ev. '

. eaem ogs

____u _ _ _ _ _ _ . _ _ . - . - _ - - - - - - ' - - - - -

R3 port 748-30 -1 Aug. 25, 1979 P;ga 6.cf 14 ,

Table VI 1

( , l Boraflex " Neutron Transmission (.06 ev) 10 Loading B Transmission ,

, 0.005 g/cm 0.655 0.014

• 0.092 i

0.024 0.027 l

=

0.041 0.014 1

l More detailed attenuation data is included in BISCO Report 748-10-1, entitled >" Irradiation Study of Boraflex."

• I 1

Additional physical characteristics of Boraflex are shown in j

Table VII, again referencing the standard B10 loading of 0.020 1

( 2 grams /cm at 0.100" thick.

Table VII

.Boraflex Physical Characteristics (typical)

Modulus of Elasticity 1000nsk Tensile Strength 200 psi Specific Gravity 1.7 (grams /ce)

Hardness 75 Shore A Temperature Stability 300*F minimum without vari-able distortion 4

(

R3 port 748-30-1 Aug 25, 1979

. Paga_7 of 14 LONG TERM MATER SOAK STABILITY The effects of long term exposure to high temperature borated water on Boraflex have been evaluated and the data obtained-demonstrates the stability of the neutron shield. under aggravated environmental conditions. Although originally int' ended as only

)

a 30 day test to simulate significant accident criteria, the-1 exposure period was extended to 6,700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> with measurements of  :

dimension and weight made at appropriate intervals. ,

l

• l 1

The borated solution consisted of deionized water with 3,000 parts per million boron in the form of boric acid added. A constant k

/ temperature of 240 F was maintained in a pressure bomb' type test vessel.

Measurement of the physical characteristics of the material after 251 days of test' exposure indicates a dimensional decrease based on the measurement of the long side of the sample piece of 0.93% and an average decrease of weight of the test sample of 0.03%.

The gas evolution of Boraflex was measured during the test period with a total of less than 1.8 x 10~3 cubic ft./ day /lb. of Boraflex being generated.

Diminishing gas evolution trend was apparent as evidenced by the fact that at the end of the exposure period the gas evolution rate was decreased to 2.1 x 10~4 cubic ft./ day /lb. of Boraflex.

(

~~

t Report 748-30-1

• Aug. 25, 1979 Pcg3 8 of 14 .

-( Extrapolation of this gas evolution data suggests that the '

~

maximum generation of gas, when Boraflex is subjected to a continuous 2409 ,

solution of borated water, effects the atmosphere of a typical ,

fuel s,torage area by less than 0.01 percent. Comp 1btedetails of the test procedure and results are available in BISCO report 748-21-1.

l IRRADIATION STUDY OF BORAFLEX i

i Accelerated '

radiation exposure tests designed to evaluate the l performance and characteristics of Boraflex to integrated levels  !

lof gamma -in excess of 1 x 1011 rads have been performed at the University of Michigan, Ford Nuclear Reactor. The test program I

and data generated are described in BISCO Report 748-10-1 j

entitled " Irradiation Study of Boraflex Neutron Shielding Material." ,.

This test program was designed to identify the physical and chemical characteristics of Boraflex under a variety of radiation levels, radiation rates and environments. Such data as was generated may  ;

be directly compared against appropriate control samples so as to further define the function and effect of many individual variables in the performance of the composite structure. .

Boraflex samples included in the irradiation tests were encased in an aluminum tube approximately 6" length x 3/4" in diameter.

The tube was filled with one of three test environments, borated water, deionized water and air, and located in available fuel  ;

positions in the core of the University of Michigan test reactor. ,

Each tube was linked to the pool surface through a vent access 9

4 -

Report 748-30-1 l

. Aug. 25, 1979 Page 9 of 14  ;

i I

pipe which in turn was attached to a distribution manifold I system to allow accurate monitoring and sample of evolved gas.

The irradiation rate of the samples positioned in the reactor core averaged 7.0 x 10 rads gamma / hour, with a concurrent neutron flux in the range of 1 x 10 14 neutrons /cm/second.

A comparable group of samples in equivalent environments were located in the spent fuel storage area in the pool of the test reactor. The gamma dose rate in this location was approximately 5

5.6 x 10 rads / hour with no significant neutron flux. Total ir-radiation in the spent fuel area was limited to 1 x 10' rads / hour gamma and is available for comparison purposes.

1 Each of the samples irradiated were evaluated for the effect of that irradiation on a number of physical and chemical characteristics. .

The following is a summary of'the data:

1. Physical and Mechanical Properties The significant physical characteristics of Boraflex monitored throughout the irradiation study were determined to be' hardness and tensile strength. Dimensional aspects of the samples were -!

noted but limited effect of the radiation was observed. The i primary impact of cumulative gamma irradiation through 1 x 1011 rads was an increase of hardness from approximately 75 shore A to 96 shore A. Tensile strength on the other hand did not vary i significantly from the pre-irradiated condition,'taking into account certain testing limitations. Although a significant decrease of flexibility of the irradiated Boraflex occurs, as can be determined by the changing ratio of hardness to tensile strength,

Report 748-30-1 Aug. 25, 1979 Pcg310 of 14

(

all evidence suggests that Boraflex, subsequent to the 1011 rads exposure, maintains ; sufficient bend tolerance to with-stand normal service and anticipated actual conditions in storage rack type application. No significant difference between samples irradiated in any of the three environments were noted in the evaluation of the results of the physical measurements.

2. Neutron Transmission Neutron transmission measurements of all Boraflex samples were made prior to and subsequent to irradiation using a l

standard energy of 0.06 ev. Evaluation of the data indicates

( no discernable trend nor effect by any environment or ir-radiation or level of irradiation effecting neutron trans-mission. Most data correlates within the 954 confidence limits i

I to the extent that it may be concluded that neither irradiation '

I or environment within the test parameters through at least H 11 1 x 10 rads has any effect on the neutron transmission of Boraflex.

3. Halogen Teachability An analysis for halogen content of the deionized water and borated water used as specific environments for Boraflex were evaluated prior, to and subsequent to irradiation of the samples in that environment.

The data indicates no evidence of increase

(

of halogen content of either test solution environment. As a result of continuous Boraflex exposure to the environments

Report 748-30-1 Aug. 25, 1979

, P ga 11 of 14 .

~

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during irradiation a minor variation of the chlorine level is noted in certain instances to a maximum level pf 29. ppm however, this variation is considered within the theoretical expected fluctuation of the test solution and the' interaction of that solution with the aluminum sample container.

4. Boron Teachability samples of the deionized water and borated water environment have,been evaluated for boron content subsequent to' irradiation of Boraflex samples within those environments to determine the stability of the boron matrix.

• The data presented indicates no discernable increase of boron in either solution._ The samples of daionized water changed in boron content by total of only 14 ppm when compared with deionized water irradiated with no Boraflex sample contained.

It is necessary to note that boron carbide conforming to ASTM C-750 -73 nuclear grade 1, will typically contain as much as 0.10 weight percent soluable boron,a quantity which can account for far more than the 14 ppa differential observed.

Analytical results conclusively demonstrate that no significant boron leaching occurs when Boraflex is subjected to deionized or borated water under concurrent neutron and gamma irradiation.

Those results also strongly suggest the efficient encapsulant function of the Boraflex polymer in preventing dissolution of normally contained soluable boron species.

Report 748-30-1

.Aug.25, 1979 P ga 12 of 14

( 5. Residual Activity Residual activity of Boraflex samples was determined following irradiation in a significant neutron flux. Activation of-certain components of Boraflex occurs primarily from normally occurring trace contaminants in the boron carbide. Specific activation data is available.

6. Gas Generation Some generation of gas is an expected, normally occurring by-prod'uct of and closed sample container in an ionizing field, resulting from continuing cross linking of~a polymeric system as well as radiolysis of the solution. - Theriefore, Boraflex samples in each of the three irradiated environments were

( monitored for gase' volution in terms of total volume, rate and composition, also evaluated were sample containers of the deionized water and borated water environment only, without samples of Boraflex present. Gas evolution measurements were taken of Boraflex in each of the environments, however even greater gas volumes were evolved from sample containers of the solutions without Boraflex. The traditional form of evaluation of the results of an experiment by subtracting the control *

. sample data is not' applicable to this phase of the irradiation experiment, since the result would have been a negative gas evolution attributable to the Boraflex. In order to evaluate worst case potential conditions, then, the gas-generated from 4

the air environment sample of Boraflex was evaluated to determine the effect of that gas on the atmosphere of the spent fuel storage chamber.

RIport 748-30-1 l Aug, 25, 1979

. j Page 13 of 14

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The following assumptions were made for the purpose of the evaluation:

A rtorage pool containing 1200 pwr type fuel positions, containing 35,000 lbs. (39,600 sq. ft.) of Boraflex is I assumed. That pool is considered to be in a fuel handling  !

building with internal dimensions of 40' x 60' x 20' ceilings,

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for a total volume of 48,000 cubic feet. It is also assumed that the unlikely event occurred that all 1200 fuel positions f

were, simultaneously filled with fresh fuel, and with a gamma emission rate of 7 x 10 7 rads per hour, and with a simultaneous neutron flux in the range of 1 x 1014 neutrons per sq. cm/second was present. The evolved gas resulting from that unobtainable

( condition would contribute less than 1/2 of it of the volume of the existing atmosphere of the fuel handling building per hour for the first hour a,nd that rate drops by about 50%

every few hours until after approximately 100, hours the rate approaches a level equivalent to less than 0.09% of the' room volume. Additionally the majority of the gas generated is in  ;

the form of nitrogen, oxygen, or CO2 ,

Application of this same concept of evaluation of the gas evolution effect in a bwr pool results in far smaller con-tributions because of the smaller quantity of poison and enormously larger room volumes that are typical.

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i Boraflex samples irradiated near the spent fuel storage area i

in each of the test environments thru a cumulative radiation

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..' Report 748-30-1 {

Aug. 25, 1979  ;

Pcga 14 cf 14 I

of 1 x 10 rads gamma evolved no measureable gas at all. This same irradiation level corresponds to the most vigorous activity of gas evolution of the samples irradiated in the l reactor core, strongly suggesting that the gas evolved is a  !

function of neutron interaction and rate and, in fact, in l application in spent fuel storage no discernable gas would be  !

evolved. For additional specific information related to the irradiation studies of Boraflex, BISCO report 748-10-1 l

entitled # Irradiation Study of Boraflex Neutron Shielding Materials" is available.

ATTACHMENTS

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A specification for Boraflex Neutron Absorbing Material dated 10/1/79 follows for reference. That specification summarizes not only product characteristics, but defines certificatica, traceability, and shipping considerations for Boraflex.

Also following is a list of technical documents, both controlled and non-controlled, which relate to the description manufacturing ,

control of Boraflex.

1

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MTdBBfEi Document No.

748-30 TECHNICAL DOCUMENTS Name Physical Product data Availability 1

748-10 Irradiation study 1 748-21 Water exposure test 1 Spec. Bid Specifications 1 M-002 Packaging, Stacking, Storage 2 M-008 Repair Procedure 2 QCP-002M Receiving Inspection - Controlled Materials 2 QCP-004H Traceability Methods, '2 QCP-006B In Process Inspection 2 QCP-006M Final Inspection 2 OCP-00BM Determination of Boraflex Acceptability 2 QCP-008M-1 10 B Loading variance request 2 QCP-009

, Control of Non-conformances 2

• QCP-010M Sampling Procedure , 2 QCS-204 Dimensional Evaluation Procedure 2 T-001 Tensile Test Procedure 2 T-002 Surface Balogen evaluation 2 M-009 Boraflex Sheet Labeling Procedure 3 QCP-002S Receiving Inspection - Raw Material 3 QCP-002B Receiving Inspection - Raw Material 3 M-003 Formulating Procedure 3 M-004 Mixing and Preparation 3 M-005 Polymerization Process -

3 M-006 Formula Detcraination *

, 3 Availability *

1. General availability. Provided on request or with bid documents

2. Controlled availabilacy. Provided af ter award of contract .

or for specific qualification as required.

3. Restricted. Contains specific proprietary data. Not distributed however may be examined at DISCO during factory audit.

eseguem4 .

MIEEEEE Document No.

748-30 TECHNICAL DOCUMENTS Name Physical Product data Availability 1

j

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l 748-10 Irradiation study 1 748-21 Water exposure test 1 Spec. Bid Specifications 1 M-002 Packaging, Stacking, Storage 2 M-008 Repair Procedure 2 QCP-002M 54ceiving Inspection - Controlled Materials 2 QCP-004M Traceability Methods, '2 QCP-006B In Process Inspection 2 QCP-006M Final Inspection 2 QCP-008M Determination of Boraflex Acceptability 2 l QCP-008M-1 B Loading variance request 2 QCP-009

, Control of Non-conformances 2

• QCP-010M Sampling Procedure 2

. OCM-204 Dimensional Evaluation Procedure 2 T-001 Tensile Test Procedure 2 T-002 Surface Halogen evaluation 2 M-009 Boraficx Sheet Labeling Procedure 3 QCP-002S Receiving Inspection - Raw Material 3 l

1

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QCP-002D Receiving Inspection - Raw Material 3 I M-003 Formulating Procedure 3 l

M-004 Mixing and Preparation 3 M-005 Polymerization Process -

3 M-006 Formula Determination

• 3 Availability *

1. concral availability. Provided on request or with bid documents

2. Controlled availability. Provided af ter award of contract -

or for specific qualification as required.

3. Rostricted. Contains specific proprietary data. Not distributed however auzy be examined at DISCO during factory audit.

eeenue ,

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. Page 1 f 3*:<'!F 9' Ud */ );..i. 'hMSPECIFICATION U. . , , , , .- .

BORAFLEX NEUTRON ABSORBING MATERIAL l l

1.0 Purpose 1.1 This specification defines the criteria for Boraflex neutron absorbing material.

2.O Scope 2.1 This specification applies to Boraflex for use as a neutron absorbing material in spent fuel storage rack applications.

3.0 Raw Materials  !

3.1 The polymer matrix shall be comprised of a silicone base thermally stabile material.

3.1.1 The polymer shall be sampled on a lot basis and evaluated specifications.

to be consistent with manufacturing 3.2 The boron component shall be in the form of boron carbide powder.

3.2.1 The composition of the boron carbide powder shall be as follows:

Total boron. . . . . . . . .70% minimum B

10 in boron . . . . . . . 17. 80' wt. % minimum Total boron plus total carbon, 974 minimum Total B 20 . . . . . . . . .34 maximum Total Iron . . . . . . . . .24 miximum l l

3.2.2 The typical particle size distribution of the boron carbide shall be: ,

98% passing through a 120 mesh size 40% passing through a 325 mesh screen 3.2.3 The boron carbide powder to be used shall be sampled on a lot basis to assure conformance

, with manufacturing specifications.

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- Revision 2

'- 10/1/79 Page 2 of 3 4.0 Boraflex Finished Product criteria' -

4.1 Physical conditions .

4.1.1 The Boraflex neutron absorber material shall be free from visible physical defects such as penetrating holes or cracks.

4.1.2 The width of the Boraflex sheet shall be as specified with tolerances of i .060 minimum.

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4.1.3 The length of the Boraflex sheet shall be as specified as a minimum value.

'4.1.4 ThethicknessoftheBoraflexs,heetggallbe as specified i .010" minimum. The B areal density specified ofas thea Boraflex minimum. sheet shall be af0 However,thakOB density shall not exceed .036 grams B /cm2 /.100" in thickness.

7 4.2 Performance criteria 4.2.1 The modulas of elasticity at room temperature shall be approximately 1000 psi.

4.2.2 The tensile strength at room temperature shall be approximately 200 psi.

4.2.3 The specific gravity at room tempera,ture shall be approximately 1.7.

4.2.4 The hardness shall be approximately _75 shore A 4.2.5 The a Boraflex neutron temperature absorber,F of at least 350 shallwithout withstand visible heat distortion.

4.2.6 Boraflexneutronabsorprshallwithstandaborated water immersion of 240 F for 260 days without visible distortion or softening.

4.2.7 The Boraflex neutron absorbing material shall withstand aEFumula.tive gamma radiation in excess of 1. 0 x 10 rads without evidence of loss of ,

functional performance characteristics and shall l

' show no evidence of swelling or loss of ability '

to maintain a uniform distribution of boren carbide.

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Revision 2 l 10/1/79 Page 3 of 3 5.0 Preparation for shipment '

5.1 Testing of the finished product shall be by procedure to verify conformance with the accepted value of the following criteria; Strength 0

B areal density

, Dimensions Appearance cleanliness 5.2 Each Boraflex sheet shall be clearly and' permanently marked with a specific lot serial number which is traceable to all pertinent documentation.

[ 5.3 The Boraflex shall be packaged and shipped in a manner consistent level C.

with the criteria outlined in ANSI 45.2.2, 5.4 Certification of conformance appropriate package shall be included with each unit of Boraflex.

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