NUllEG / CR-1053NRL Report 8357

Notch Ductility Degradation of Low Alloy Steelswith Low-to-Intermediate Neutron Fluence Exposures

J. R. II AwilionNE

Thermostructural Staterials BranchAtaterial Science and Technology Division

January 14,1980

Prepared for U.S. Nuclear Regulatory Commission

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NAVAL RESEARCII LABORATORYWashington, D.C.

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The extent and trend of Charpy V (C ,} > notch ductility changes in reactor vessel materials withy

fluences of 1 X 1018 to 10 X 1018 nicm- 1 MeV were investigated with several thick sectionsteel plates and submerged arc weld deposits irradiated at 288 C (550 F). The materials were fallyrepresentative of reactor vessels now in service and had copper contents ranging from 0.10 to0A0% and phosphorus contents ranging from 0.008 to 0.020'"c. Material irradiations were per-formed in a 2 MW pool reactor.

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20. Abstract (Continued)

The steels with high radiation sensitivity indicated an onset of notch ductility change atfluences of ~ 1.5 X 1018 n/cm2 by an elevation in the ductile-to-brittle transition temperature.Reductions in upper shelf were not observed at this fluence level but were in the range of 0 to 15'iat ~ 4 X 1018 2n/cm and between 15 to 44% at ~ 8 X 1018 2n/cm .The data trend suggests apower law relationship of upper shelf reduction to fluence at low-to-intermediate fluences.

The C transition temperature elevation and upper shelf reduction with irradiation are com-y

pared to embrittlement projections by U.S. Nuclear Regulatory Commission Guide 1.99. A limitedexperimental comparison of radiation effects to dynamic fracture toughness and notch ductilityis also presented.

iiSE cuRIT V cL ASSIFIC A TION O F Twis P AGE (when Data Entered)

CONTENTS

INTRO D UCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.

M ATE RI ALS . . . . . . . . . . . . . . . . . . . 1.. ... . . .......

MATERIAL IRRADIATION . . . . . . . 3..................

R E S U LTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 3..............

Observations for 1 to 2 X 1018 n /cm 2 . . . . . . . . . 5......

Observations for 3 to 4.5 X 1018 n/cm2 5..... .....

Observations for 6.5 to 9.5 X 1018 n/cm2........ 6..

Observations for >10 X 1018 2n /c m . . . . . . . . . . . . . . . . . . 6Trend of Upper Shelf Reduction at Low-to-

Intermediate Fluence . . . . . . . . . . . ......... .... 6Fracture Toughness (K ) Degradation . . . . . 7j . ........

DISCUSSION . . . .... ........ ....... .......... 7

CONCLUSIONS . 8... . . . ..... . . . .... ...

ACKNOWLEDGMENTS . . . 8.... . ... .. .... ........

REFERENCES, 9...... .. ........ ................

iii

NOTCII DUCTILITY DEGRADATION OF LOW ALLOY STEELS WITil

LOW-TO-INTERMEDIATE NEUTRON FLUENCE EXPOSURES

INTRODUCTION

The embrittlement of reactor structural steels by neutron fluence typically is assessedfrom changes in Charpy-V (C ) notch ductility. The progressive increase Ln embrittlementy

with neutron exposure is known to be non linear with fluence (n/cm2 > 1 seV) and,in addi-tion, has been shown to be dependent on the content of copper and phosphorus impuritiesin the steel. Through C data compilations and analyses, radiation embrittlement trendsy

have been evolved for application in reactor vessel design and for guidance of fracture safevessel operation. One example of the development of embrittlement versus fluence curves isthe U. S. Nuclear Regulatory Commission (NRC) Guide 1.99 [1] . While significant progresshas been made, trend development efforts have been impeded greatly by a lack of radiationdata for the extremes of the fluence range of interest. Projected end-of-life (EOL) fluencesfor many currently operating reactor vessels are on the order of 3 to 5 X 1019 n/cm , A2

large volume of data exists for 2 to 4 X 1019 n/cm2 fluences; however, data for exposuresbelow this fluence interval are scarce. This study was undertaken with the objective of im-proving knowledge of both the extent and trend of C notch ductility changes in reactory

vessel steels (plate and weld metals) at low to-intermediate fluences, that is, between 0.1 andI X 1019 2n/cm . A second objective was to obtain an experimental assessment of the levelof conservatism in current embrittlement projection methods.

Property changes at less than EOL fluences have become of increasing importance as aresult of minimum notch ductility levels set forth in the Code of Federal Regulations(10CFR50) [2] and the ASME Code, Section III [3]. A C upper shelf energy level of aty

least 68 J (50 f tlb), for example,is required to index the reference nil ductility tempera-ture, RTugi , f or fracture toughness iaracterization of the vessel material. Additionalconsiderations are recommendations and specifications for the selection of reactor vesselsurveillance materials [2,4]. For surveillance, the materials normally included in the pro-gram are those predicted to be most limiting with regard to the setting of pressure-temperature limits for fracture safe operation. IIere, it is conceivable that the materials withthe highest fluence accumulation may not always be the limiting materials because of radia-tion sensitivity differences. Therefore knowledge of radiation effects to a spectrum ofmaterials for fluence conditions less than the vessel beltline fluence is important.

MATERIALS

Several commercially produced plates and weld deposits were selected for the investi-gation. The materials are identified by NRL code number and composition in Table 1 andare fully representative of reactor vessel materials now in service. The A302-B plate is alsothe ASTM reference correlation monitor steel used extensively in reactor surveillanceprograms [5] .

* Manuscript submitted September 12,1979.

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IIAWTilOltNE

Table 1 - Test Materials *

Chemical Composition, w t%

Material NitL Code Cu P C Mn S Si Ni Cr Mo V Other

A302-II Platch F26 0.20 0.011 0.24 1.34 0.023 0 23 0.18 0.11 0.51 0.01 At 0.038

A533-Il Plate N27' O.13 0.008 0.17 1.21 0.007 0.20 0.56 d 0.50 0.02 Al 0.015EBB 0.10 0.009 0.19 1.28 0.013 0.25 0.61 0.04 0.55 0.004

EDil 0.14 0.009 0.20 1.31 0.012 0.22 0.62 0.08 0.59 0.004

3M U' O.12 0.011 0.20 1.26 0.018 0.25 0.56 0.10 0.45 - Al0.034

A533 B S/A Weld MY 0.36 0.015 0.14 1.38 0.012 0.22 0.78 0.07 0.55 -

W1 0.35 0.020 0.09 1.45 0.013 0.68 0.57 - 0.39 -

NitL 1 0.19 - - 1.43 - - 0.56 0.08 0.36 -

NRL2 0.29 - - 1.56 - - 0.65 0.08 0.39 -

NitL 3 0.30 - - 1.53 - - 0.68 0.08 0.40 -

NitL 4 0.16 - - 1.51 - - 0.58 0.08 0.37 -

NHL5 0.39 - - 1.60 - - 0.58 0.10 0.39 -

NRL6 0.16 - - 1.49 - - 0.58 0.09 0.39 -

NRL7 0.27 - - 1.42 - - 0.56 0.06 0.36 -

NRL8 0.32 - - 1.51 - - 0.68 0.07 0.39 -

W 0.29 0.020 0.09 1.50 0.014 0.56 0.62 0.16 0.37 < 0.01

62N(1)f 8 0.18 0.019 0.08 1.55 0.008 0.60 0.55 0.17 0.38 0.0162N(2,f 0.24 0.013 0.08 1.42 0.008 0.57 0.50 0.07 0.37 0.01

f63N 0.31 0.017 0.10 1.02 0.010 0.65 0.69 0.09 0.42 0.01

' Material thickness range: 15.2 to 26.6 cm 'IAEA Reference Plate (IISST Plate 03)ASTM A302-B Reference Plate (5) 'Appro imate compositionb

8'NRL A533-B Demonstration Melt [8] Two weld filler wires usedd Not determined

The C, specimens ( ASTM Specification E-23, Type A) were taken from the quarterthickness location in plates and from through thickness locations in weld deposits. Speci-mens of the A-302 B and A533 D plates were oriented, respectively, to represent the longi-tudinal (LT) and transverse (TL) test orientations [6] . Weld metal specimens were orientedwith their long axis perpendicular to the welding direction. In all cases, the axis of the speci-men notch was perpendicular to the surface of the material.

A limited study of the irradiation effect to dynamic fracture toughness (Kj) was alsoaccomplished using fatigue precracked Charpy-V (PCC ) specimens and J-integral assessmenty

methods. The Ky was computed from specimen energy absorption to maximum loadcorrected for specimen and test machine compliance. Electric Power Research Institute(EPitI) procedures and requirements for Kj determinations were s.tisfied [7] .

2

NRL REPORT 8357

MATERIAL IRRADIATION

Material irradiations (Table 2) were conducted at a nominal 288 C (550 F) at theState University of New York at Buffalo using its 2 MW pool reactor (UBR). Irradiationtemperatures were monitored by multiple thermocouples in each specimen array. Theambient neutron flux was on the order of 7 X 1012 2n/cm -sec. Fluence determinationswere based on measurements with iron neutron dosimeter wires placed among the speci-mens. For the UBR fuellattice positions used, the calculated spectrum fluence (<!>")and

Jthe fluence based on an assumed fission spectrum (<! ') have the relation:

J4>'' = 1.22 <! ' (> 1 MeV). (1)

Table 2 - Material Irradiation Experiments

Experiment No. Target Fluence Material Codes

1018 n/cm2 > 1 MeV

1 1 Plates F26, N27, Weld MY

2 5 Plate N27, Weld MY

3 7 Welds W,62N(1),63N

4 10 Weld 62N(1)

5 1 Plates EBB, EDB, Weld W1

6 3 Welds NRL 1 to NRL 5,NRL 7, NRL 8

7 6 Welds NRL 1 te NRL 5,NRL 7, NRL 8

8 11 Weld NRL 6

9 18 Plate 3 MU

(C , PCC )y y

RESULTS

Experimental C results for the individual materials are illustrated in Figs.1 through 17y

and are summarized in Table 3. Fluences listed in each figure are calculated spectrumfluences(<bCS). In the discussion below, ductile-to-brittle transition behavior is indexed tothe 41 J (30 ft-lb) temperature unless noted otherwise.

3

ilA%TIIORNE

Table 3 -Summary of Charpy-V Notch Ductility ChangesWith 288 C (550 F) Irradiation

Transition Temperature Upper Shelfyg. ,

1018n/cm2 Unirradiated Irradiated gMaterial / Code

DIMeV) C, 41J C, 6 8J C, 41J C, 6 8J dia ted

@ )*C *F 'C 'F *C 'F 6*C A* F *C 'F A*C A*F J ft-Ib J ft.lb AJ

A302.B PlateF26 1.2 -18 0 10 50 4 40 22 40 32 90 72 40 117 86 117 86 0

A 533-Il PlateN27 1.2 -62 -80 -43 -45 -62 -80 0 0 -40 -40 0 0 187 138 1R7 138 0

6.6 -62 -80 -43 -45 -34 -30 28 50 -9 15 33 60 187 138 171 126 16

21.0a -62 -80 -43 -45 16 60 78 140 46 115 69 160 187 138 ~134**99 53

EBB 1.3 -12 10 13 55 f 2 635 $ 14 $25 29 85 17 30 137 101 137 101 0

EDil 1.3 -1 30 21 70 '8 65 19 35 41 105 19 35 160 118 160 118 0

3MU 17.0 -1 30 29 85 43 410 44 80 77 170 47 85 138 102 136 100 ~0

S/A WehlMY 1.2 -34 -30 -15 5 -4 25 31 55 21 70 36 65 145 107 142 105 ~0

6.6 -34 -30 -15 5 99 210 133 240 124 255 139 250 145 107 103 76 4226.Os 34 30 -15 5 141 285 175 315 174 345 189 340 145 107 76 50 69

WI 1.4 -29 -20 2 35 2 35 31 55 - - - - 94 69 94 69 0

NRL6 16.0 -23 -10 7 45 88 190 111 200 107 225 100 180 107 79 77 57 30

bNRLl 4.2 -15 5 4 40 27 80 42 75 82 180 78 140 107 79 103 76 4

9.5 -15 5 4 40 66 150 81 145 104 220 89 160 107 79 90 66 17

NRL2 4.2 -34 30 41 105 57 135 58 105 96 205 56 100 104 77 91 67 139.5 -34 30 41 105 93 200 94 170 123 265 89 160 104 77 81 60 23

NRL3 3.9 -9 15 27 80 57 135 67 120 93 200 67 120 100 74 96 71 4

8.5 -9 lb 27 60 85 185 94 170 121 250 94 170 100 74 31 60 19

bNRL4 3.6 -18 0 18 65 27 80 44 80 46 115 28 50 98 72 90 66 8

7.6 -18 0 18 65 52 125 69 125 77 170 58 105 98 72 76 56 22

NRL5 3.9 16 60 52 125 -1 30 53 95 113 235 61 110 83 61 83 61 0

9.0 16 60 52 125 88 190 72 130 127 260 75 135 83 61 79 58 4

N R1, 7 3.2 -26 -15 7 45 13 55 39 70 49 120 42 75 111 82 106 78 5

6.7 -26 -15 7 45 43 110 69 125 79 175 72 130 111 82 90 66 21

bNHL8 3.9 -9 16 24 75 63 145 72 130 93 200 69 125 106 78 90 66 169.0 -9 15 24 75 91 195 100 180 116 240 92 165 106 78 79 58 27

W 8.9 -29 -20 -1 30 60 140 89 160 - - - - 104 77 63 48 39

62N(1) 8.9 -29 -20 4 40 60 140 89 160 102 215 97 175 103 76 79 58 2412.1 -29 -20 4 40 71 160 100 180 - - - - 103 76 68 50 35

63N 7.8 4 40 ~38-100 135 275 131 235 - - - - 87 64 49 36 38

* Prior data.bUpper shelf values taken at 160*C (320* F).

4

NRL REPORT 8d57

Observations for 1 to 2 X 1018 n/cm2

Figures 1 through G present data for the low fluence condition. The results indicatethat radiation effects on notch ductility are first becoming significant at this fluence level.Transition temperature increases are on the order of 14 to 31 C (25 to 55 F) with the high-est copper content materials (welds MY and W1) showing the greatest irradiation effect. Incontrast, upper shelf reductions are notably absent. It thus appears that the transition tem-perature elevation begins with fluence in advance of the upper shelf reduction and that themechanisms responsible for each are not the same.

In Figs. 2 and 5, a higher neutron exposure of 6.6 X 1018 n/cm2 (intermediate fluencelevel) is found to produce both a transition temperature elevation and an upper shelfdecrease in plate and weld material. The weld shows a much greater irradiation effect thanthe plate and this is a direct consequence of its higher copper content. Further irradiation to

2~2 X 1019 n/cm , on the other hand, produced a sirailar increase in transition temperaturefor the plate and the weld, that is,50 C vs 42 C. Nonetheless, the overall radiationsensitivity of the weld is much greater than that of the plate.

Referring to Fig.1 (ASTM reference plate), the upper graph shows unirradiated condi-tion test results obtained for the plate at a location displaced from the location of theirradiation test specimens. In the lower graph, results obtained from " control specimens"from the same location as the irradiated specimens are indicated and illustrate the impor-tance of making property checks in critical testing. Referencing the control data, a 22 Ctransition temperature elevation is measured. A shift of $11 C (insignificant) would bemeasured relative to the mean of the data band. Obviously, inappropriate unirradiated con-dition data can inject not only scatter, but also considerable confusion into radiation trendanalyses. Moreover,it is seen that " errors"in reference condition properties have thepotential for masking the benefit of refinements in experimental procedures, includingdosimetry.

Observations for 3 to 4.5 X 1018 n/cm2

In this fluence interval, both a transition tem;.erature elevation and an indication ofupper shelf reduction were observed for all but one (Weld NRL 5) of the materials tested.Tests of the plates were not conducted in this range; however, a prior evaluation of theASTM reference plate at 5.5 X 1018 n/cm2 [5] produced t 3G C (65 F) transition increase.(Upper shelf level was not established). Smaller traneition increases would be projected forthe other, lower copper content plates. Overall, transition temperature elevations ranged fromabout 39 to 100 C (70 to 180 F). Upper shelf reductions ranged from 0 to 15%.

The irradiation effect is generally found proportional to material copper content. Thenonconformance of Weld NRL 5 to this pattern at this fluence level is being investigated. Noexplanation can be offered at this time.

5

IIAWTilORNE

Observations for 6.5 to 0.5 X 1018 n/cm2

liere,large transition temperature elevations ranging from 69 to 133 C (125 to 240 F)were observed for the welds along with large reductions in upper shelf energy (15 to 44%).A greater radiation resistance was found for plate N27 and would be characteristic of com-panion plates of the same general copper content {8] . Of special interest, Figs. 7 and 8demonstrate that upper shelf levels can be educed to 68 J (50 ft.lb) or lower at this inter-mediate fluence level. In the case of weld 63N (Fig. 8), the upper shelf was reduced to 49 J

n/cm , Isolation of the metallurgical reason (s) for such poor upper(36 ft-lb) by 7.8 X 1018 2

shelf retention should be an urgent task. Nonetheless, the results show the need for evalua-tions of intermediate fluence effects as well as EOL fluence effects in developing embrittle-ment projections.

Observations for > 10 X 1018 n/cm2

2A few of the materials were irradiated to fluences greater than 10 X 1018 n/cm . Thedata, given in IJigs. 2,5, and 9, indicate a trend of increasing radiation embrittlement withincreasing fluence but at a much reduced rate. This is most evident in Fig. 5 and is consis-

9 . On this point, a large volume of data from test reactortent with earlier findings [5,8,3 }n/emirradiations exist for> 2 X 10 2 fluences which clearly show increasing radiationeffects with fluence. For survei!!ance irradiations, on the other hand, recent data by West-inghouse suggest a saturation of radiation effects at ~1 X 1019 n/cm2 when the flux is low,

n/cm -sec [10] . Confirmatory research, however, is clearly needed. For one, a2~5 X 1010closely controlled set of test reactor experiments should be performed to verify the sug-gested saturation, using flux and fluence levels comparable to those of the power reactorresults. Secondly, higher fluence irradiations will be important to confirm that the effect isnot temporary, that is, restricted to a certain fluence interval only, since EOL fluences canbe high. It is noted in Fig. 9 that the increased embrittlement can almost be masked by datascatter when the increment of additional fluence is small, such as 3 X 1018 n/cm2

Trend of Upper Shelf Reduction at Low to-Intermediate Fluence

Analysis of the data relating percentage upper shelf reduction and fluence for the weldmetals in the low to-intennediate fluence interval suggests a relationship of the form:

Upper Shelf Reduction (%) = A($")",

where A and n are constants for a tr.aterial. The value of A varies with material and is anindicator of material radiation sensitivity. The exponent, n, on the other hand, appears rela-tively material independent and has a value of about 2.3. Welds NRL 2 and NRL 8 which

18 n/on2 depart fromcxhibited the largest upper shelf reduction of the materials at 4 X 10the primary data pattern. In these two cases, lower values of n are required to fit the data.Investigations to further explore the trend relationship are in progress.

6

NRL REPORT 835'l

Fracture Toughness (K ) Degradationj

A limited investigation of relative fracture toughness degradation with irradiation wasconducted using the IAEA reference plate (HSST Plate 03, Nith Code 3MU). The PCC,specimens and C, specimens were commingled in the irradiation assembly to achieve anidentical exposure history. The results, given in Fig.18, show a good agreement of transi-tion temperature elevations measured by the t= .) test methods. Evidence of a possible corre-lation of PCC, and C results have also been found by an EPRI-NRL research program ony

A533 B steel [11] . One plate, for example, exhibited an increase in C, 41 J temperature of92'C (165 F) and an increase in 100 MPa @ temperature of 86 C (155 F) after~3 X 1019 n/cm2 at 288 C (550 F). If the tentative correlation is confirmed by additionalPCC, tests now in progress and by dynamic compact toughness tests, the value of the largevolume of C, irradiation data generated in prior years will be greatly enhanced.

DISCUSSION

Graphs given by the NRC Guide 1.99 for the projection of C notch ductility changesy

with fluence are reproduced in Figs.19 and 20. Both figures take into account the role ofimpurity copper and phosphorus contents in radiation sensitivity development. One objec-tive of the present study was to test the conservatism of NRC Guide projections in the low-to-intermediate fluence range, recognizing that only sparse data were previously availablefor defining property-change limits in this interval. Entry of the new data on the graphsindicates that the NRC Guide may be overly conservative in projecting upper shelf reduc-tions at low fluences and at intermediate fluences. A lesser degree of overconservatism isnoted for its transition temperature projections.

In Fig.19, the data suggest that upper shelf change might be more accurately describedby a set of bilinear curves such as used to project transition temperature behavior (see Fig. 20).Similar evidence from surveillance programs, however, would be required before new curvescould be promulgated. Unfortunately, surveillance data appear to be more scattered in thisformat and are illustrative of a broad range of performance at low fluences. One source ofscatter has been discussed with the ASTM reference plate results (Fig.1). Appreciable reduc-tions in upper shelf have also been observed for some long term reactor surveillance irradia-tions to further cloud the analysis.

In Fig. 21, measured and projected transition temperature increases are compared.Here, a broad scatter is evident, particularly at the higher embrittlement levels. The sourceof the scatter has not been established but may be due partially to the lack of a term fornickel content in the projection formula. That is, data are available which indicate thatnickel content can cause a reenforcement of the primary copper content effect on radiationsensitivity [12,13].

To summarize, the new data suggest that current penalties at low fluence could bereduced provided that reasons for inconsistencies in surveillance data become understood.The possibility for a reduced penalty appears to be greatest for upper shelf energyproperties.

7

IIA %Ti!OltNE

CONCLUSIONS

Charpy-V notch ductility changes produced by low-to-intermediate neutron fluence at288 C (550 F) have been investigated using several plate and weld metals representative ofreactor vessel construction. The irradiation effect in general was found to increase withmaterialimpurity copper content. Primary observations and conclusions of the study werethe following:

1. At low fluences of 1 to 2 X 1018 2n/cm , high radiation sensitive steels begin toexhibit changes in notch ductility. Transition temperature elevations in excess of 11 C(20'F) but not upper shelf reductions were observed at this fluence level.

2. Fluences of 3 to 4.5 X 1018 n/cm 2 produced transition temperature elevations of39 to 100 C (70 to 180 F) and upper shelf reductions of 0 to 15'A.

3. At intermediate fluences of G.5 to 9.5 X 1018 2n/cm ,large transition temperatureelevations of 69 to 133 C (125 to 240'F) and large reductions in upper shelf energies of 15to 44% were observed. One weld exhibited 49 J maximum after 7.8 X 1018 n/cm .2

4. For low-to-intermediate fluences, a relationship of upper shelf reduction to fluenceof the form: Iteduction (7;) = A ('I'")", is suggested by the data for most of the materials.The value of A varies with material radiation sensitivity; the value of n is relatively materialindependent.

5. NltC Guide 1.99 may be overly conservative in projecting upper shelf reduction atfluences less than 5 X 1018 n/cm2. A lesser degree of overconservatism was indicated by thedata for transition temperature projection.

G. The trend of log percent upper sitelf reduction with log neutron fluence appearsbest described by a set of bilinear curves.

7. A correlation between transition temperature elevations measured by dynamicPCC and C, test methods appears poss.io e from initial experimental comparisons.y

ACKNOWLEDGMENTS

This study was sponsored by NRC's Reactor Safety Research Division, Metallurgy andMaterials Branch. The continued NRC support of NRL research is sincerely appreciated.Special thanks are extended to C. Z. Serpan, P. Albrecht, and P. N. Randall for helpfuldiscussions during this investigation.

The author expresses his appreciation to 11. E. Watson, W. E. IIagel, J. D. Forsyth, andT. A. Zimmerman for their respective contributions to experimental phases of theinvestigadons.

8

NftL REPoltT 8357

ItEFERENCES

1. " Effects of Residual Elements on Predicted Radiation Damage to Reactor VesselMaterials," Regulatory Guide 1.99, U.S. Nuclear Regulatory Commission, Office ofStandards Development, Washington, D.C., Apr.1977.

2. " Fracture Toughness and Surveillance Program Requirements," Appendices G and 11,Title 10, Code of Federal Regulations, Part 50 (10CFR Part 50), U.S. Atomic EnergyCommission, Federal Register 38,136 (17 Jul.1973).

3. ASME Boiler and Pressure Vessel Code, Section III, Sube: tion NB (Class 1Components), NB-2331, American Society of Mechanical D gineers, New York,1974.

4. " Recommended Practice for Surveillance Tests of Light Water Cooled Nuclear Powerlleactor Vessels," ASTM Recommended Practice E185-79 (pending publication).

5. J.R. llawthorne," Radiation Effects Information Generated on the ASTM ReferenceCorrelation-Monitor Steels," ASTM DS-51, American Society for Testing andMaterials, Philadelphia, PA, Jul.1974.

6. R.J. Goode, " Identification of Fracture Plane Orientation," Material Research andStandards, MTRS A, Vol.12, No. 9, Sep.1972, p. 31.

7. D.R. Ireland, W.L. Server, R.A. Wullaert, " Procedures for Testing and Data Analysis,"Task A-Topical Report, ETI Technical Report 75-43, Effects Technology, Inc., SantaBarbara, California, Oct.1975.

8. J.R. IIawthorne, "Purther Observations on A533-B Steel Plate Tailored for ImprovedRadiation Embrittlement Resistance," NRL Report 7917, Naval Research Laboratory,Washington, D.C., Sep. 22,1975.

9. J.R. llawthorne," Strength and Notch Ductility of Selected Structural Alloys AfterIfigh. Fluence,550'F (288 C) Irradiation," NRL Report 7813, Naval ResearchLaboratory, Washington, D.C., Dec. 2,1974.

10. S.E. Yanichko and J.N. Chirigos, " Assessment of the Validity of Trend Curver in Pre-dicting Embrittlement of Reactor Pressure Vessels," Attachment to NS-TMA-1843,Jun.19,1978.

11. J.R. Ilawthome, ed., "The NRL-EPRI Research Program (RP886-2), Evaluation andPrediction of Neutron Embrittlement in Reactor Pressure Vessel Materials, AnnualReport for CY 1978," NRL Report 8327, Naval Research Laboratory, Washington,D.C., August 30,1979.

12. J.R. Ilawthorne, J.J. Koziol, and S.T. Byrne, " Evaluation of Commercial ProductionA533-B Steel Plates and Weld Deposits with Extra Low Copper Content for RadiationResistance," Symposium on Effects of Radiation on Structural Materials, ASTM STP683, American Society for Testing and Materials (J. A. Sprague and D. Kramer, Eds.),1979, pp. 235-251.

13. J.R. llawthorne and E., Fortner, " Radiation and Temper Embrittlement Processes inAdvanced Reactor Weld Metals," Trans. ASME, J. Engrg. for Industry,71WA/PVP-11,American Society of Mechanical Engineers, New York,1971.

9

IIA %Tl!ORNE

-50 o 50 10 0 (( 2 88 (* C )T I I I ))

6-IN. A302-B PLATE(ASTM REFERENCE)

(f t-ib)YS = 70.1 hsi M

10 0- P =0015% -'M

Cu =O22%

eo- UN!RRADIATED _ ios

60-gse_n

- 81

/ |40- / / - 54

/

gzo- e - 27

W #D i ei e i i i io 7, n

10 0- - 136

"80- UNiRRAD.

- 10 8oCONTROL # * IRRADIATED 550*F(288'C)

so- / /0 1.2 x 1058 2n/cm g>j y,y),)Cs - 81/

7 - 40"F (22*L)40-

|- 54

- 40*F (22*C)f '420- '

- 27

'2b bb ('F)

012 0 -40 4o 12 0 200

TEMPERATURE

Fig.1 -Charpy-V notch ductility of the ASTM A302 D reference plate. The upper graphshows baseline data for the plate. The lower graph compares control test results withresults for low fluence irradiation. The baseline data band is also shown for reference.

10

NitL ItEPOftT 8357

.I00 -SO O SO 100 tSo 200 N, i i i i I 3

e,a,e IRRADIATED 550*F (288'C) (J)

'"[ 6-IN A533-B-1 PLATE (CODE N27) -2t7YS = 68 2 ks. 12 x 10 e1

p . coo 8s o /*

WO- Cu = 013% o 3'" ~

UNIRRAD * 6 6 x 10,,12 6

12 0- I~

21 x 10''. ,

g"- * ' ~ ~. .

-w oO so- e -os

*M- * - 81

+M*' - - mov te9*cl* ,

4o-* "

-"

e .8 * "

0 . { CS . n/cmr 3 j u,y

to---cy~+ , ,

-i4ov t7e c)2 ci- 27

! ' * 'ido 2Ao 456i'il

' '# '0- -so 0eo 320

TEMPERATURE

Fig. 2 - Charpy V notch ductility of an A533-Il plate, Code N27, from the N!tL demonstrationmelt [8] before and after irradiation to three fluences

-50 0 50 10 0 150 200 (*c)I i i 1 1

'" ""'""" ''''

14 0 -8-lN A533 B PL ATE (CODE EBB) <aG IRRADI ATED 288C (550F)

( 10 Cu, 009 P, 61 Ni) i 3 a 10'' n/cm > IMeV, 4c5 - 180I

12 0 -

- 150

000 -

O104

O- 12 0

80 -3

$$ to

~ 90w cc - a e,

8o 30 F (17 0)- 60

40 - f

s 25F (I-- 3020 -

,

Ui i ! ! ! I I I ! I ' I i0

-12 0 -40 40 120 200 280 360 (* F )

T E MPE R AT URE

Fig. 3 - Charpy V notch ductility of the A533 Il plate, Code EBB, after low fluence irradiation

.

11

IIAWTliORNE

-50 0 50 100 180 200 (*C)I i i i i I

(f t -it) O UN;RRADIATED

i40 - 8-IN. A533 -8 PL ATE (CODE EDB) *e iRRAoiATro 2eeC (ssor)

( 14 C u, OO9P, 62 Ni) 1 3 a 10'' n /c m' > 1 Me V, 4C5 - 18 0

120 -

0 11 80

o - 150

400 -

- 120> 80 -

S Oy 5 - *60 L*

e *O e 3S F (19C)

40 - 60-

35F (19C)20 - e/ ^ 30

Al I I I I I I I I I d- Io o-120 -40 40 12 0 200 280 360 (*r )TE MPER AT URE

Fig. 4 - Charpy V notch ductility of the A533-D plate, Code EDB, after low fluence irradiation

-SO O SO 100 ISO 200 ( 8 (*C)I i r i T 7

'" **3 i A D MO*F (288*G (_ 10-IN A533-B-1 S/A WELD (CODE MY) _,

YS * 72 O kse * }'' * n /cm2 , g y,y

,,a_ P =oOes ,,,,0,.*- i63Cu * 0 36% /

* /*o*'

,gg_ (#41RRAD o, tos

_,

g 6 6 m tote>

8=- / -c8*

.m 76

2 6 m O''*

8 (3 C O*F (189'C),

- 54240*F _(t33*C1 / ,7

__ 33,7 g,q* SS*F

20-/ 8 e( 3:* C )

_

_ g * -f -g- --- --- -g 4- yg-~*--3g * - ---g-- %- yq,730 o

TEMPERATURE (*F)

Fig. 5 - Charpy-V notch ductility of submerged arc (S/A) weld, Code MY, before and afterirradiation to three fluences

12

NRL REPORT 8357

-tCO -50 0 50 10 0 150 (*C

i i | I i 1

9 3/4-IN A533-B S/A WELD (CODE WI) ,,o vaRnAoiATEo( 35Cw, C20 P, 5 7 Ni) e IRR ADIATED 286C(s50F),

I 4 a lO''e Am' > 1 V'V. M g

(f t-Ib) - 12 0

80 -

, O' h 69 - 90so - 7",

* O / - 60" 40 - /w

W - /<55F (3tC)

U - 3020 -

rt i 1 1 I i | | 1 I t0 o

-Kc -80 0 60 ico 240 320 ( *F )

TEMPERATURE

Fig. 6 -Charpy-V notch ductility of submerged are weld, Code W1, after low fluence irradiation

-50 0 _50 10 0 150 ?ll (, r

(as,) A 5k3-8 S/A WELD (W) O UNtRR ADIATED [NRL) (yp )g7

110 -9 IRR ADIATED 550 F(288 C) 750g 6 9 x 10'enfem2, i v,y,e n

rG .00 - e

*- 650

-9 90 - .

!*

*, ,

6 80 N 552(Ji

(f t-lb)

80 - Oo 0 77

7'-

69 [REF CURVE) . 9960 /

| O'4s# #>

*40 * Il E '42 "d')

w -- - 16 0 F - - --(89 C)

20 9- 30

L E 35 m.:n(IRRAD )

Td 40 Y2O 550 280 360 55 ii12 0 4

TE MPER AT U RE

Fig. 7 - Charpy-V notch ductility of submerged are weld, Code W, after intermediate fluenceirradiation. Postirradiation dynamic yield strength determinations from Dynatup load vs timetraces are also shown in the upper graph and m Figs. 8 and 9.

13

IIAWTilORNE

-50 0 ._50 'M ISO 2N4 ee_Lc)2

? A 533 8 S/A WELD (63N) O UN6F. A ADI ATE D (N RL )

[ e e IRRADIATED SSO Fl288 C) (VP 28

N 7 8 s lO e /c.2 iu,4 4cs 750i n%

y %~~ es

;; im . e.a

7 650y 902

hL 80 " '* 552,

(J)If t it) t2O

80

90, . - - - - - - - - - 64

/

$ 40 ,[ 6

$ O ,,i-- - p 'i (tE I5mds- -- 2 35 r _c 3ic)

20 /- 30

___ _ _- i- _ . .. ..____.i _. ___ qq_oo_a,

T E MPt N Af bRE

Fig. 8 - Charpy V notch ductility of submerged are weld, Code 63N, after interrnediatefluence irradiation

'y _ _. y _ _ .-_ __ _ .?O __ ___150_ 2m_g 2m___(*c_ )0 ';

Ikli) A533- S/A WEL D (62N) O UNIRR ADIATE D (NRL } gyp,)F IRRADIATE D 550 F (289 C)| gg

# 8 9 x IO e ,jg 2 , ; y,y, gl es 750

kesO 12 I m 80 eofc.2 > i y,y, g

. .;ma *a 6so

Y 90 e

!2

I I I I I 1 I 1 1 ' ! I I a8 80 gy(J)

(f t-tb) - 12 0

00 O O76

O O (LE - 46 mds)/

90w O 2 e myW D

p - 175F -- e e - * 50, O\ - 60j (9fC) s -.o* 40 (L E - 4 4 mils)/ 2w ,/ - _ . -_ - g sor __. -

IO F0 3020 ( )a LE 35 miss (IRRAD)

.1 1 _. . I .._l_ ____ I . ._1___ _.1 3.I.__ l _-_1 _1_-- _ _.1-g _o

T E MPE R A f uRE

Fig. 9 - Charpy-V notch ducti'ity of submerged arc weld, Code 62N(1), after irradiation to twointermediate fluences

14

NRL REPORT 8357

-Se o So too i5o 200 t C)i i i i i i

O UNIRRADIATEoA533-8 S/A WELD (NRL 1) e IRRADIATEo 288 C (550F) (J)

(f t lb) y'' = 4 2 m tote /cm2g,iu,yg- 15 0

n

3 PoSTiRRAD. ANNE ALEb 399 C (750F)-168 h100-

S - 12 0

80- - _ _ , GC ~ ~ fge"i

g 60-e - 90

3

O') a +w m -60

40_

~A + 42 C (75 F)

20- - 30

I e I i l i oI 'I *o 2 a i

A333-B S/A WELD (NRL 1) IRRADIATED 288C (550F )'}"= 9 5 a 101enfe,2 (>1Mov) -15 0e

foo-

-12 0- - ~ ~

80- - 73-0# W 7o

> a-90

g Go- , ,

W~

40- e ,

+ + etch 45F)*

20-- 30

e

' I * ' I ' ' ' 'o o-12 0 -40 40 12 o 200 280 360 44o (*F)

TEMPERATURE

Fig.10 - Charpy-V notch ductility of submerged arc weld, Code NRL 1, after irradiation to two fluences.Limited results for postirradiation heat treatment are also shown in this figure and in Figt.res 11 to 17

15

IIAWTIIORNE

-50 0 50 100 15 0 200 ('C )i i 1 1 I

If'*M O UNTRRADIATED

12 0 -t,533-8 S/A WELD (NRL 2) e IRRADI ATED 288 C (550F ) (J)

'' = 4 2 a 10'' n/c m2 g,,y,y350

m POSTiRRAD ANNEALED 399 C (750F1-168h100 -

20 93 - 12 0

30 -

__77

# 67 - 90$

j5 - [ *,-

40 -

60-

m3 *+ SBC (105 F)/

' i ! # l A '' ' I IO O

(f t-Ib) (p12 0- A533-B S/A WELD (NRL 2) * ' "$U ^ **C' '

} = 9 5 m 10 n/cm2 (> t MeV) _ i$os

POSTIRRAD ANNE ALED100 - 0 343 C (650F) -168 h

a 399 C tT50F) -16Bh-12 0

00 '

--ry. 3_ 11

hE 60 - 360

- %3>

$ + /" ,'m - 60a40 - ,o

"94 C (170 F )3* -*

' II ' ' ' ' ' ' OO-

-12 0 -40 40 12 0 200 280 360 400 (* F )

TEMPERATURE

Fig.11 -Charpy-V notch ductility of submerged are weld, Code NRL 2, after irradiation to two fluences

16.

NRL REPORT 8357

-50 0 50 10 0 150 200 (* C )r i;,

O UN;RRADIATED y)' '*RAU' ATED 28B C (550F)A533-B S/A WELD (NRL 3) 2 ,ip ,y318

(f t ta pesa 3 9 m 10 n /c m g

3 POSTiRH AD ANNE ALED 333 C (750 F) -:08 h~

10 0 -

07- 12 0

80- 2,o 3a77T' - 905 ,

$ 60 -

76/

o' ~ws ,<O

,

' --

20 . p' ff- + * 67c (12c ri--30

1i i i ! __ iI 1 iif , Oo

A533-B S/A WELD (NRL 3) y)e IRRAD|ATED 268 C (55CF)

pen . 8 5 10 n ,t m2c,qu ,v3 _ i5318

3 POSTiRR AD ANNE ALED 399 C (750F) -168h100 -

- 12 0*

80- 74w

|E . - 906060- ,

~

40-

,f -- 94c (170 F)

20 -/+ * - 30' ,p-

1 L 1 e r ii e i e 0o-12 0 -40 40 12 0 200 280 360 440 (* F )

TEMPERATURE

Fig.12 -Charpy V notch ductility of subinerged are weld, Code NRL 3, after irradiation to two fluences

17

!!AWTl!OltNE

-50 0 50 10 0 ISO 200 (* C )I 6

O IJN:RR ADiAT EDA533-B S/A WELD (NRL 4) o IRRADIATED 288 C (550r) (J)(f t-It,)

pc' = 3 6 : 10'8 n /c m2g>iy ,y)- 15 0

_ G POSTlRRAD ANNEALED 343C (650F) -168 h

O80 - 83 - 0

O7p

e a 69>g 60 - O ," .

* - 90

W *< [40- - 60

) /3 --+ 44cf90F)

20 - /- 30

' 'C' ' ' P ' ' ' '' I

O

A533-8 S/A WELD (NRL 4)( D-tM e IRRADIATED 288 C (550 F)

pcs= 76 t0 n /cm2(>gy,y)- 15 0

18

POSTIRRAD ANNEALED10 0--0 343 C (650 F) -168 h3 399 C (750 F) -168 h

-12 080 - '

o 60 - 23 CS -90y

$ f . . _ . ,Az + f

- ," s

40 -

s' e' ~

+ +' 69 C (125 F I--' Y' - 3020 - -

0 t i i 'l a t i >

'

o-i20 -40 40 12 0 200 280 360 440 (*F)TEMPERATURE

Fig.13 -Charpy-V notch ductility of submerged are weld, Code NRL 4, after irradiation to two fluences

18

NRL REPORT 8357

50 0 50 10 0 150 200 (*C)i T i i

O UP,.RR ADIATED ;9

A533-B S/A WELO (NRL 5) e IRRADIATED 288 C (550 F)S 2h***39atO n/cm g,1 MeV) 50

( f t-ib)3 POST 1RRAD ANNEALED 399 C (750F) -168h

100-- 120

80 -

b -90* 89$ 60-- 0 ,- 6Y .m

G40 -

r O ---_. G 5 3 C (95 F )~ N

20 -

e

' ' '---A-- ' -' ' - A'U * - - 0'O

A533-B S/A WELD (NRL 5)

2 ,;y,q) . 15 0p *' = 90 m 10'' n /cm g

10 0- 120

80 -

to..90

-61

b 60I , ,

. - 60,o _

+ 0'' 72 C 1130 F )

20 9 4- 30

I O' f I 'l l' l* '0-120 -40 40 120 200 280 360 440 (* F )

T E M PER ATURE

Fig.14 - Charpy-V notch ductility of submerged arc weld, Code NRL 5, after irradiation to two fluences

19

liAWTIIORNE

-50 0 50 100 150 200 (* C)i I . i

O UNIRRADIATED'

ei ADIATED 288 C (550F1A 533-8 S/A WELO (NRL 7)(f t Ib) f ** = 3 2 a 10'8 2 ,gy,y)gn /c m

12 0 -3 POSTIRRAD AWE ALED 343 C (650 F) -168 h

-15 0

O -12 09 8210 0 - O w

78O Or W

h 80 --90

$ '* eO 9, 96040- o t e39 C (70F)~*

20 - /6 - 30

I I li I i f f i i0 a

A 533-0 S/A WELD (NRL 7) e tRRAD!ATED 288 C (550 F) (j)(f t-ib)

f *' * 6 7 a 1018 n/cm2(>gy ,y}

3 POSTIRRAD. ANNEALED 333 C (750F) ~120 -

168 h

-:D- 922 - 170

100- 82

ej 80- * 6 66 -90

3w ez +W e

- 6040 - e+ -~e 69C l125 F )

20 -_. 30

0 1 i es ji e , , ,1 0

-12 0 -40 40 120 200 280 360 440 (* F )

TEMPERATURE

Fig.15 - Charpy V notch ductility of submerged are weld, Code NRL 7, after irradiation to two fluences

20

NRL REPORT 8357

-%O O 50 100 150 200 (* C )1 6

1 1

O UNiRR ADiATED

A533-8 S/A WELD (NRL 8) G IRRADIATED 288 C (550 F) (J)n /c m2 (3,y,y)

_ ,5Ut at) g cs, 3 9 , jois@ POSTiRR AD ANNE ALED 343 C (650 F) -16S h

,

8 88 - 12 0

~F ~~,,..- 7980 -

2 v

:* o- 30

,0 .

g 60E + /

so.' y' o

ac -

72 C Ii30 F )O ---

I ' '- I I ' ' '' a OO

A533-B S/A WELD (NRL 8) ,33; J '.*"iATED 288 C (550 F)

y"= 9 0 a 10 n jc,2 g,1Mov) 15018( f t-lb)

3 NSTiRR AD. ANNE ALED 399C (75Cf ) -1E8 h100-

- 120

'I -- 7 980

>g

- 90

g 59:y 60-W +

~

40"00 t (teG F1, --

I b L 0' ' '

O420 -40 40 120 200 280 360 400 (* F )

TEMPE R ATURE

Fig.16 -Charpy V notch ductility of submerged are weld, Code NRL 8, after irradiation to two fluences

21

IIAWTIIORNE

-50 o so too ipo 200 <*s )

O UNIRRADIATED

A533-B S/A WELD (NRL 6) . IRRADIATED 288 C (5500 gi{"= 16 a lo*n/cm2(3gy,yj-Ibl

~

@ PoSfiRRAD A%EALED 543C (6SoF1-168rtoo

- i20> 80 -

, - 79= .y *

- sow 60 - *

= = - $7g

40_ O ' 60

3O Inc (200r),

.

o 1 I A 1. # 1 e i'' >

o-tzo -4o 40 i20 zoo 2eo 360 44o (* F )

TE WPE R ATURE

Fig.17 - Charpy V notch ductility of submerged are weld, Code NRL 6, after intermediatefluence irradiation

22

NRL REPORT 8357

100 0 100 200 ( cig

1.-1240

(k sis in) A533-B PLATE (3 MU, HSST03) {l'*AT G* 265(TL ORIENT ATION)

-

*~---\- s- - I gp

240 c. e UNIRRADIATED" "-*^[ |" ''

'

ce IRRADIATED 288C (550F);210*

1.5 10'' nicm2 - 1 MeV,

i o. - K ELASTIC| ee K ELASTICI PL ASTICu

180* eg

| 180y

.z ,-4

f f3

8 120' ;120

e - - - - - - 44C (80F)

60 60o

Yp L

O' '-- ' - - -'

O

(f t-lb)(J)

.30o UNIRRADIATED

, 120 e IRRADIATED

o *2 ; 100y *

'" o 120

800

o e

~~. * e 47C (85F) 6040 o *

e* * 44C (80F)

,/ e

0 Lt. ,' '

- 160 - 80 0 80 160 240 320 400 (*FlTEMPERATURE

Fig.18 - Comparison of Charpy V notch ductility and dynamic fracture toughness forthe IAEA A533 B reference plate, Code 3MU, before and after irradiation. Fracturetoughness was determined using fatigue precracked Charpy V specimens and J-integralassessment procedures.

23

IIAWTIiORNE

PREDICTED DECREASE IN UPPER SHELF ENERGY60 60

-

40 - */. COPPER ',- - 40r

h30 - M TL WELDSO- 30

$ O.35 - 0.30-'

a O.30 - O.25- />:20 - 025 - 020- - 20g 0.20 - 0.15- '

g3 0.15 - 0.10- ,gI 10 -

'' ~/ - 10

s : / A o :2 ~

/ -

[- / -

: 5 -

| g a -

$ - / 3 -

8 'o - / -

' Ab' 7' ' ''' I 1 ''t''''''''hIO ' ' ' 0

2 x 10 '7 1018 1,2 goI9 6 x 10'9FLUENCE , n /cm2 ( E > lMev)

A302-8 A533-8 S/A WELD

e F26 .20 Cu Q MY .36 Cu 5 NRL2 .29 Cu VW .29 Cu

A533-B $ WI 35 Cu 3 NRL3 .30 Cu V 62N(1) .18 Cuo N27 .13 Cu d NRL6 .16 Cu O NRL5 .39 Cu 7 63N .31Cu

o EBB .lO Cu A NRL I .19 Cu Q NRL7 .27 Cus

O2ED8 .I4 Cu 6 Nr.L4 .16 Cu 5 NRL8 .32 Cu

Fig.19 - NRC Guide 1.99 graph for projecting the upper shelf reduction with fluence.Results of the present stady are superimposed. The data suggest that a set of bilinearcurves might better describe the upper shelf trend. The dashed line represents thebehavior of submerged are weld, Code MY.

24

NRL REPORT 8357

PREDICTED ADJUSTMENT OF REFERENCE TEMPERATUREyd gT 400

400 - As[40 + 1000 (% Cu-0.08) + 5000(% P-0.OO8))[f /lO ]t/2i9 gp g

"" 300d 300 - ,,

-

3 -

d - 2006 200 - , ,

' -$ - Ou.

! 10 010 0 --

940 7 ,

# A :i : #'

E- g4 / \

-

OO ~ | 0.30 0.25 0.20 / O.15 0.lO %Cu LOWER LIMIT ~

8 % P = 0.012 % Cu = 0.08S 0.35 /

[ % P = 0.OO8/ 2b

[ I i 1 i l i l i t il 'Ib Og

.[o.I I i 1 1 if1I I I I IE O i 1 e ie

19*d 2 x10 1018 10'8 6 x 1037

FLUENCE , n/cm2 (E > l MeV)

A302-8 A533-8 S/A WELD

# F26 .20 Cu Q MY .36 Cu E NRL2 .29 Cu VW .29 Cu

$ WI .35 Cu 3 NRL3 .30 Cu V 62N(I) .18 CuA533-Bo N27 .13 Cu d NRL6 .16 Cu O NRL5 .39 Cu V 63N .31Cu

01 EBB .lO Cu A NRL I .19 Cu Q NRL7 .27 Cu02EDB .14 Cu A NRL4 .16 Cu 5 NRL8 .32 Cu

Fig. 20 -NRC Guide 1.99 graph for projecting the reference temperature elevation withJuence. Results of the present study are superimposed. Note the degree of conservatism in theNRC Guide projections at low fluence.

25

HAWTIIORNE

LOW ALLOY PV STEEL PLATE AND WELDS0 50 100 150 200 (*C)

h g.p)'

(*C)o - 200%

z g 300 -

Y I IU 150*

Sa T.

8 6 *.

E 200 - T.**e

$, 100*

*'8 e

0::) i 9 *O s 100 *

do PLATE - 50w# o * WELDk i LIMIT LINE

PROJECTIONe

1 ' 'o o o1 0 100 200 300 (* F)EXPERIMENTALLY MEASURED aT

(C,41 J INDEX)

Fig. 21 -Comparison of NRC Guide 1.99 projection oftransition temperature elevation with experimentalmeasurement for the individual plates and welds. A widevariation in the conservatism of the NRC Guide projec-tions is noted.

26

DEPARTMENT OF THE NAVY [ 's

POSTAGE AND FEES PAIDNAVAL RESEARCH LABORATORY DEPARTMENT OF THE NAVYs

Washington. D C 20375 3,

000 316.%. t j

OHICIAL SUS. NESS

PENALTY FOR PRIVATE USE,5300

i

,

s --

,.

120555031837US IJRC 2 ANRSSECYBR ANCH CHIEFPUBLIC UCCUNtNT RGONHST-LCadyW A S H I t. G T J ti DC 20555

'N- \

'

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