ML20023E053
| ML20023E053 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/21/1982 |
| From: | Beavan L PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20023E052 | List: |
| References | |
| 906624, NUDOCS 8306070106 | |
| Download: ML20023E053 (59) | |
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, GA 14315[REV.11/80) (FSV-80-221 ISSUE
SUMMARY
TITLE: RESULTS dF PGX GRAPHITE SURVEILLANCE E R&0 APPROVAL LEVEL 3 FORT ST VRAIN REGION 25
] S DISCIPLINE SYSTEM 00 C. TYPE PROJECT 00CUMENT NO. ISSUE N0s LTR.
0 17 RTE 1900 906624 A QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SE!SMIC CATEGORY ELECTRICAL CLASSIFICATION QAL I SC-2 CAT-I NA.
/ PREPARED APPROVAL ISSUE (g ISSUE DATE BY DESCRIPTION h ENGINEERING QA fg PROJECT MA L.A.
Beavan G.B.Engl D. R.J. % L' tdl.Pettycord D. Kowel Initial Issue WO 2970366 OCT 311992 320T24 W4/eo-. 10gv 0 e CONTINUE ISSUE
SUMMARY
ON GA FORM 1485-1. NEXT INDENTURED DOCUMENTS 906099 REV SH REV SH 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46- 47 48 49 50 51 52 53 54 55 56 REV SH 1 2- 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 8306070106 830519 P6GE 1 0F 59 PDR ADOCK 05000267 P PDR
ee T*
. s,,3ENERAL ATOMIC CO .PANY
' GA-1484 d> " RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. Issue TABLE OF CONTENTS
- 1. INTRODUCTION------------------------- 4 -
- 2. TEST ELEMENTS------------------------ 4 2.1 Materials----------------------- 4
. 2.2 Reactor Service----------------- 5 2
E 3 PREDICTIONS OF OXIDATION------------- 5 5
- 4. PROCEDURES--------------------------- 5 a
a a 4.1 Specimen Removal---------------- 5 5 f 4.2 4.3 Initial Inspection-------------- 6 0xidation Profile--------------- 6
=
i 5. RESULTS------------------------------ 6
.h 5.1 Specimen Removal---------------- 6
] 5.2 Non-Destructive Examination----- 7
= 5.3 0xidation Profiles-------------- 7 j 5.4 Predictions--------------------- 8 8
2 6. DISCUSSION--------------------------- 8 s C
; 6.1 Specimen Retrieval and 5 Experimental Procedures--------- 8 3., 6.2 Oxidation----------------------- 9 E
7 CONCLUSIONS--------------------------11
- 8. REFERENCES---------------------------11 APPENDIX A---------------------------43 APPENDIX B---------------------------44 4>
Pge 2
3ENERAL ATOMIC CC '.PANY
' GA-1484 TITLE:
+ RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. '**
906624 A LIST OF TABLES Table Fage 1 Preirradiation Characterization of PGX Surveillance Specimens--------------------------- 13 2 Region 25 PGX Surveillance Specimens Post-irradiation Dimensions and Weight------ --------- 14 3 3 Region 25 PGX Specimen Weight Changes------------ 15 E l 4 Oxidation Remaining in Specimens After Profiles Cut---------------------------------------------- 16 4 i 5 Summary of Characterization for Impurities in
@ PGX Sample--------------------------------------- 17 5 .
=
1 5 2 E 2 8 LIST OF FIGURES
.=
A
,s Figure i Page G
3 1 Location of PGX Inserts in Reflector Element----- 18
$ 2 PGX Surveillance Test As sembly------------------- 19 )
3 Region 2 5 As sembly Record------------------------ 20 1 4 Oxidation Rates of PGX - Laboratory Data--------- 21 5 Location of PGX Surveillance Elements------------ 22 6 Postirradiation Examination Technique------------ 23 7 Appearance of Surveillance Specimens After Re a cto r S e rvic e---------------------------------- 24 , 1 i 8 Predicted vs Measured Burnoff Profiles of PGX Surveillance Specimens ( Re gion 2 5 ) --------------- 2 6 9 Oxidation Profile , Specimen T200A---------------- 27
+ 10 Oxidation Profile , Specimen T100A---------------- 35 Rge 3 l l
l
. '. "3ENERAL ATOMIC CC. .PANY
' GA-1484
+ RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. Issue 006624 A
- 1. INTRODUCTION This report describes the postirradiation examination (PIE) re-sults obtained from the PGX graphite surveillance test element re-moved from FSV reactor region 25 Five test elements containing PGX graphite surveillance specimens were inserted into the bottom re-flector region of the FSV reactor at the first refueling [Refs. 1,23.
The PGX surveillance program was funded by PSC to obtain data from the FSV reactor operation on the state of oxidation of PGX graphite in the reactor. By comparison between surveillance specimen perfor-mance and predictive computer codes the actual condition of the PGX 4 core support blocks may be calculated. The retrievable test elements g exposed PGX surveillance specimens to reactor conditions which were g nearly the same as experienced by the PGX graphite core support 3 blocks in the reactor. The extent of graphite oxidation in the sur-g veillance specimens is assessed by periodic removal of test elements 2 and examination of their PGX specimens. Comparison of the measured g oxidation to the predicted oxidation of the surveillance specimens e provided a basis for assessing the oxidation of the core support blocks using the same predictive methods.
]
Test element R-90-1 was removed from region 25 after approxi-a mately 2 calendar years in service. The test element contained 8 PGX 5 surveillance specimens from billet 6484-112 and 8 specimens from 3 billet 6484-138. The PIE of the 16 PGX surveillance specimens is the j subject of this report. A l 8 j 2. TEST ELEMENTS 5 g 2.1 Materials E 2 Each test element contained 16 PGX surveillance specimens taken Z from two billets of PGX graphite. The properties of comparison PGX specimens taken from the same locations in the same billets were re-l ported earlier [2]. The PGX surveillance specimens were designed to be inserted into the machined reflector elements at eight coolant l hole locations in each element as shown in Figure 1. Into each cool-l ant hole location were inserted one H-327 graphite spacer, two PGX l surveillance specimens, and one H-327 graphite cap as illustrated in Figure 2. One PGX specimen from each parent PGX billet was placed in each I of the 8 holes. The position of the PGX specimens was varied every 2 holes so that billet 6484-138 specimens were uppermost in the block in holes I, II, V, VI and specimens from billet 6484-112 were upper-most in the other four holes. The specimen loading record is pre-sented as Figure 3. Initial weights and measurements of the-surveil-lance specimens are given in Table 1. 4
^
. '.' GA-1484 3ENERAL ATOMIC CO TPANY
+ N RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. Issue Laboratory oxidation tests which were performed on companion PGX specimens were summarized by Figure 4 taken from Reference 2.
2.2 Reactor Service The test element was positioned in column 7 of region 25 of the FSV reactor (Figure 5) during June 1979. The region 25 test element was removed from the reactor in May 1981. Temperature, power and moisture levels in the reactor were obtained from the FSV plant data logger system for the time period of interest. 3 3. PREDICTIONS OF OIIDATION E
$ The CSBBO-3 computer code was used to predict the oxidation in i the PGX surveillance specimens based upon actual reactor performance j data obtained from the data logger. The predicted oxidation of the
- PGX specimens was reported elsewhere [3]. Predictions of PGX oxida-E' tion were based upon the PGX oxidation rate shown as a solid line-in
$ Figure 4, which is 1000 times the H-451 graphite oxidation rate.
e Since only one PGX oxidation rate was assumed, the predicted oxida-E tion varied only with temperature and moisture level, with no differ- [3 entiation between the 2 PGX billets. i Consequently, the predicted oxidation was constant between spe-I cimens in the same coolant hole, but varied between coolant holes.
! Dunn [3] predicted the overall weight loss for each specimen and also
-8 the burnoff profile or density gradient in each PGX specimen. The y detailed predictions of Dunn [3] provided an excellent basis for y
comparison to actual measurements of oxidation. E
] 4. PROCEDURES I E l 4.1 Specimen Removal The PIE of region 25 PGX surveillance specimens was performed following the published specifications [4]. The test element was placed in the Hot Service Facility at FSV in February 1982,'8 months after removal from the reactor. According to PSC, the activity of the test element block was 30 mR/hr gamma and 500 mR/hr beta at contact, and 20 mR/hr gamma with 250 mR/hr beta at one foot from the block.
Due to the low activity of the element, an individual was sent ! into the Hot Service Facility to manually remove the specimens using a special removal tool (2]. Removal of the specimens required approximately 15 minutes in the facility, resulting in a whole body dosage of 2 mR to the individual. After removal, the specimens were stored in H-451 graphite crucibles in a can and shipped to GA. When received at GA on March 15, 1982, the activity of the 16 specimens
+ plus caps and spacers was 2.5 mR/hr gamma at 8 inches and 5 mR/hr beta at 8 inches. page 5
I
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3ENERAL ATOMIC CC. PANY GA-1484
, TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. inueA 906624 4.2 Initial Inspection Specimens were removed from 1 crucible at a ' time to maintain order and identity. Each specimen was visually inspected,. measured, then sealed in a tared plastic bag and weighed. Measurements of outside diameter (0.D.) were made at three locacions [5] using hand held micrometers. Length measurements were made at 2 locations [5]
using a Heidenhein MT 10 electronic gage. Specimen weight was deter-mined using a Sartorius microbalance accurate to 1 x 10-4 grams. Photographs were then made of each specimen. 4.3 0xidation Profile Oxidation profiles were measured on each specimen following the i procedures of Ref. 6. In summary, the procedure consisted of dimen-E sioning and weighing the specimens, then removing a thin (0.0025 to j 0.005 inch) layer from the inner cylinder bore of the specimen and a remeasuring and weighing the specimens. The density of the layer re-I moved was calculated from the weight and measurements of the remain-t ing specimen. This process was repeated for 10 to 30 layers, result-
)
.g ing in a profile of density (oxidized weight loss) versus distance from the original surface. The procedure is shown schematically in
. Figure 6.
2 j Due to the slight radioactivity of the specimens, the profile determinations were performed in a glove box. One chamber of the 3 j glove box contained a precision lathe which was used to machine the
; layers from the inner bore. Machined specimens were transferred from E the machining chamber through an isolation chamber into the mea-2 surement chamber of the glove box. In the measurement chamber, the
.$ inner diar .iters of the specimens were measured using a Mauser 6700/9H E bore gage coupled to a Heidenhein electronic micrometer head. The E resolution of the total measurement system was 1 x 10-3 mm. The E
thicknesses of the layers measured were 64 x 10-3 to 130 x 10-3 mm. l i Specimens were weighed on a Sartorius model 1207 MP2 balance which
- E was mounted on isolation pads to minimize vibration. Resolution of weight was 2 x 10-4 grams, (approximately 0.2% of the minimum layer weight).
- 5. RESULTS 5.1 Specimen Removal Removal of the PGX specimens from the test element block took
- less than 15 minutes. The specimen removal tool performed adequate-l ly, however the tool did not function smoothly in holes near the block edge (i.e., hole #VI). In several holes the tool had to be in-serted and tripped several times to engage the spacer and lift the stack out. Two hands were required to remove 4 of the specimen stacks from the tocl to the storage crucible. When specimens must be removed from test assemblies by remote devices, it will be necessary l
to use 2 fully articulated manipulators to complete the task. Page 6 l
. ^3ENERAL ATOMIC CC lPANY
' GA-1484 q, TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE
-FORT ST VRAIN REGION 25 Document No. 906624 Ime A The overall appearance of the test element block was excellent.
5.2 Non-Destructive Examination PIE measurements and weights of the surveillance specimens are summarized in Table 2. The specimens appeared to have grown a frac-tion of a percent. Specimen weight was 0.2 to 0.3 grams less than at insertion, a decrease of 0.8 to 1.25. The specimen weight loss mea-sured at the initial inspection (Table 3) and again at the start of the profile determination were in excellent agreement. The measured weight losses were about 20% of the predicted weight losses [33. Overall weight loss in the PGX surveillance specimens averaged j 0.805 in the 100 series (billet 138) specimens and 0.93% in the E billet 112 specimens (Table 2). The billet 138 specimens showed E little variation with a standard deviation between specimens of 0.02 5 wt 5 or 2.5% of the mean. Greater variation was noted in the billet i 112 specimens which had a standard deviation of 0.16 wt 5 or 17% of t the mean. j Visual examination of the PGX specimens revealed a distinct dif-
. ference between the 200 series specimens (billet 6484-112) and the j 100 series taken from billet 6484-138. The cylinder bore of the 200 5 number specimens appeared highly oxidized with a rough surface text-ure as shown in Figure 7a. The 100 series specimens exhibited less 6
s apparent strface oxidation as shown in Figure 7b. The difference in gf oxidized surface texture was apparent even in specimens which had the E same total Weight loss as shown in Figures 7c and 7d. Photographs of j each of the 16 specimens are included in Appendix B.
$ 5.3 0xidation Profiles
.s j All 16 PGX surveillance specimens were machined to determine the i density profile (oxidation profile) relative to the original inner j cylindrical bore of the specimen. Figure 8. summarizes the oxidation profiles measured on the 16 PGX specimens. The 200 series specimens from billet 6484-112 were oxidized to 30% to 45% weight loss at the coolant channel surface (inner cylinder bore), while the 100 series were oxidized to only 8% to 15% weight loss at the surface. The oxi-dation decreased rapidly with distance away from the surface in the 200 series. The 100 series specimens exhibited very flat oxidation profiles with oxidation levels of about 15 remaining at a distance of 1.2 mm (0.040 in.) away from the surface.
l Oxidation profiles were plotted for each specimen in Figures 9 and 10. The data presented in Figures 9 and 10 were smoothed at measurements at which the Mauser bore gauge head was changed to the next largest head. Calibration runs with unoxidized graphite had shown I.D. measurement errors when the bore gage head was changed. l The data were smoothed by deleting the weight and measurements at the point of the head change. As a result, the layer density calculated at that location was calculated from a double thickness layer. Pge 7
' GA-1484
3ENERAL ATOMIC CC .PANY
+ RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. Inue 906624 A After the specimens were machined to determine the oxidation profile, the remainder of each specimen was measured to calculate its density. The densities of the specimen remains were tabulated in Table 4 and translated to burnoff (density change). The 100 series racimens showed low levels of burnoff in the remaining material af t.:.r the profiles had been measured.
5.4 Predictions Results of the CSBBO-3 code calculations were well documented by Dunn [3]. Predicted weight losses for the surveillance specimens are 4 su'marized m in Table 3 of this report. The most severe and least g severe oxidation profiles predicted for the region 25 specimens are g shown in Figure 8. In all cases, the CSBBo-3 code predicted higher a levels of oxidation and more severe oxidation profiles than actually bserved in the surveillance specimens. I 2 5 I 6. DISCUSSION j 6.1 Specimen Retrieval and Experimental Procedures a g The overall retrieval and PIE of the surveillance specimens was y performed smoothly according to plan. The tool used to remove the
.5 specimens from the test element block required 2 hands at times for j successful operation. Due to the low radioactivity of the test ele-
.g ments, specimen retrieval will probably be best accomplished by man-ual removal of the specimens in the PSC Hot Service Facility. Should 3 remote handling be required, 2 articulated manipulators will be nec-
.5 essary for easy operation of the removal tool.
E e During the PIE of the specimens, the largest and only signifi-I cant systematic error was found in the measurement of the inner dia-2 meter of the cylindrical specimens. Oxidation profile determinations l can vary by 2% burnoff for an error of only 0.0025 mm (0.0001 inches)
.in the I.D. measurement. The Mauser gage which was used had a reso-
! lution of 0.001 mm (0.00004.in.), however the oxidized graphite sur-l face was easily indente'd by the gage head at points of contact, lead-ing to errors in measurement. The errors were most pronounced when gage heads were changed because the next larger gage head exerted a higher indenting force against the graphite surface. Therefore the data were smoothed by deleting the weight and dimension measurements at the point of the head change. The resulting layer density was l calculate.; from a double thickness layer. The pocential for this ! problem was recognized in the early planning of this PIE and a non-contact laser metrology system was budgeted. The laser based system was not purchased due to vendor reservations regarding errors in
~
specimen alignment and their effect on the accuracy of the laser measurement. However, such a measurement system, fitted with a custom alignment collett apparatus, should be seriously investigated
+ for future PIE for two reasons: (1) potential improved accuracy of the measurement; and (2) adaptability to remote measurements.
Pg 8
^
. '. 3ENERAL ATOMIC CO .PANY
' GA-1484 p, TITLE: RESULTS OF PGX GRIsPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. I" A 906624 6.2 Oxidation Both the overall oxidation and the oxidation profiles observed in the PGX surveillance specimens were less severe than predicted.
These results confirm the conservatism of the CSBBO-3 code predic-tions, which were based upon a design PGX oxidation rate of 1000 times the H-451 rate as shown by the solid lines in Figure 4. Laboratory oxidation tests of the PGX surveillance sample population [2] had resulted in measured oxidation rates which were less than the design rate as shown by the data in Figure 4. The surveillance results were qualitatively consistent with laboratory data. The oxidation behavior of the PGX surveillance specimens removed
']E from region 25 was similar to the behavior observed in high velocity laboratory oxidation tests at 7000C. In both the 7000C high velocity ~
[ lab test specimens and the PGX surveillance specimens, the graphite from billet 112 displayed higher overall weight loss and steeper j 4 oxidation profiles. These results suggest that billet 112 specimens i oxidized at faster oxidation rates than the billet 138 specimens. E' However, low velocity laboratory data showed the converse; billet 138
.@ showed highest oxidation rates. These results illustrate the diffi-
= culties inherent. in extrapolating laboratory oxidation results to 2 describe behavior under reactor conditions. The laboratory test con-
! ditions which most closely simulated reactor conditions produced oxi-dation behavior similar to actual in-reactor oxidation, while typical 3
j standard oxidation tests were less discriminatory. I g Differences between laboratory test results were probably due to
-3 changes in mass transport and in states of catalytic activity in the
.e PGX graphite. Several studies [7-8] have found widely varied oxida-S tion behavior in PGX graphite due to different test conditions. The 3 results of PIE of region 25 confirm the importance of accurately 8 modeling actual operating conditions when investigating oxidation j behavior in the laboratory.
The PGX surveillance specimens removed from region 25 exhibited the same qualitative differences in weight loss as observed in oxidation rates from lab testing. The variation in overall weight loss in the billet 138 specimens was only 2.5% of the mean compared with a variation of 4.7% in the laboratory data. Specimens from billet 112 had a standard deviation in overall weight loss of 17% of the mean which was consistent with the 16% found in laboratory tests at 586 hours [2] .
Likewise, the oxidation profiles found in the specimens differed considerably from billet 138 to billet 112. The 200 series specimens l from billet 112 underwent up to 40% weight loss at the surface, but j oxidation decreased rapidly away from the exposed surface (Figures
- 8,9). PGX billet 138 material experienced less than 20% weight loss at the surface, but the oxidation profile was much flatter (Figures 8,10). The difference in oxidation profiles most likely arose due to Page 9
'3ENERAL ATOhllC CO 'PANY GA-1484 TITLE: RESULTS OF-PGX GRAPHITE SURVEILLANCE
+
FORT ST VRAIN REGION 25 Document No. I""' 906624 A differences in mass transport and in the complex catalysis of oxida-tion in PGX. Billet 112 contained approximately twice the impurity level as billet 138 including significantly higher levels 'of Fe, S, and Cu (Table 5). Iron is a known catalyst for graphite oxidation. Rapidly oxidizing graphite generally exhibits steeper oxidation profiles as observed in the 200 series surveillance specimens. In the 100 series specimens, low level oxidation extended further into the depth of the specimens as shown in Figure 8 and Table 4. The flatter profile with a longer tail is characteristic of more slowly oxidized graphite. However, the differences in overall oxidation between billet 112 and 138 material averaged only 18%, much less than j would be expected on the basis of the oxidation profiles. The PIE of E the next surveillance test element to be removed from the reactor { (Region 30, refueling number 4) will show if the specimens from bil-lets 112 and 138 continue to exhibit approximately equal overall j burnoff. J h Due to the difficulties of I.D. measurement, the accuracy in
.@ determination of burnoff was about 22% burnoff. At the tail end of e the oxidation profile 5, the slope of the actual profile was difficult 2 to determine due to the inaccuracies. In the bil.l et 112 specimens
! (200 series) the profile was steep enough to be determined quite accurately. However, the shallow slope of the billet 138 specimens 3
j made the profile determination more difficult. Consequently, the
; burnoff remaining in the specimens at the end of the profile deter--
g mination was tabulated in Table,4.
~C
.$ The profile data combined with Table 4 indicate that the oxida-6, tion penetration of the 112 billet specimens had ended at depths of E In the billet 138 material, the oxidation penetration 0.9 to 1.1 mm.
5 still existed at depths of 1.5 to 2 mm although the level of burnoff j was only 0.5 to 1.5 wt %. In both cases, the depth at which oxi-4 dation equaled 1 wt % was considerably less than the 2.3 mm predicted by CSBBO-3 code. The surveillance specimens from region 25 experienced consider-ably less oxidation than predicted by the CSBBO-3 code. Strength and modulus of oxidized PGX graphite can be calculated according to Equation (1) [7]. S
= ,xp
-mx ; L (3)
So Eo where S,E = strength, or modulus, of oxidized graphite So,Eo = strength, or modulus, of unoxidized graphite X = oxidation level (fractional burnoff, i.e.,
+ 10% = 0.10)
@ 10
1 DENERAL ATOMIC CC .PANY
' GA-1484
, TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 l
Document No. I" A 906624 l m = 5 for PGX. 1 The strength or modulus of PGX graphite containing an oxidation profile can be calculated from Equation (1) at increments along the oxidation profile [7]. Since the experimentally observed oxidation i profiles of the surveillance specimens were considerably less severe than predicted by CSBBO-3 code, the actual reduction in graphite strength was also much less than would have been predicted. 7 CONCLUSIONS PGX surveillance specimens removed from region 25 exhibited i significantly less oxidation than predicted. Overall oxidized weight E loss averaged only 20% of the predicted values. Actual penetration j depth of oxidation into the specimens was only about 50% of predic-a tions and the level of burnoff in the oxidized volumes was j considerably lower than predicted, h The CSBBO-3 code conservatively modeled the behavior of the PGX
.j specimens in reactor. Code predictions and experimental measurements e were in good qualitative agreement. Quantitative errors were prob-j ably primarily due to conservatism in the assumed oxidation rate.
$ PIE methodology worked well. A non-contact, highly accurate j method for measurement of specimen inner diameter could increase the
; accuracy of the measured profiles, particularly .in the low burnoff g tails. ,
8
.e Laboratory oxidation experiments must approximate actual reactor 5 conditions to accurately predict graphite oxidation behavior. The 5 better the laboratory approximation to reactor conditions, the better
,_8 the correlation between laboratory and in-reactor behavior.
s 3
- 8. REFERENCES
- 1. " Test Plan for In-Reactor ' Surveillance of Grade PGX Graphite,"
Document 18-R-29/A. December 12, 1978.
- 2. "FSV PGX Surveillance - Final Report," Document 17-R-18/A, August 7, 1979 3 " Prediction of Graphite Burnoff in FSV Surveillance Samples -
Cycle 2," Document 906223/A, September 25, 1981.
- 4. " Test Specification for PIE of PGX Surveillance Specimens (Region 25)," Document 906099/A, August 25, 1981.
- 5. " Procedure for Nondestructive Examination of PGX Surveillance Specimens," Document TP-061, February 9, 1979.
- 6. " Procedure: Oxidation Profile Determination for PGX Surveillance
-> Test," Document TP-059, January 19, 1979 Page 11
f'% 3ENERAL ATOMIC CO. .PANY
- GA-1484
+ TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. 906624 laus A 7 Price, R.J. and L.A. Beavan, " Strength of Nonuniformity Oxidized PGX Graphite," G A-A16270, May 1981.
- 8. Morgan, W.C. and M.T. Thomas, "The Inverse Oxidation Phenomenon,"
Carbon, 4 E a i i i e 2
.s
! M l .o i z l l l
+
- 12
l . I Notations in this column indicate where changes have been made c) Table 1. Preirradiation Characterization of PGX Surveillance Specimens. N Y ! 5 j D mm ! DATE l' IIl 8 '
#N O$
i OPERATOR Kim ! HE3 c $$ RECORDER QA #ID
,Le ll
~
C . I
~A &
' <o
( 'Y d !' 1 $' ' j Gl REFLECTOR REGION 75 yg i - k, p_G,.uk ,,. q, =
- m I
' A D B EO 2 ALL MEASUREMENTS ARE!N INCHES a
( g%
=m h
! SPECIMEN LENGTil OUTSIDE DI AMETER INSIDE DIAMETEH WElGHT VISUA su U
.,, . . f ,mm F NUMBER A-A 8-8 C-C D-D E-E F-F G-G ~ GRAMS ^ ^^E # ^ ' ' C E g y 7'/ m el ,2762 .1752 f.2970 /a929 /.2??i 6258 42s1 2K 3369 1. 7 ';7 3 5 d
'/' 7 o o si .1'76 7 ,1767 /.2977 (3976 1.2737 .626I 6257 25.7075 /. 7 75 g g O 7'/OFC_ 316 *t ".4755 f. 299 2 1.2??/ t .29'/0 _G24L .6260 26. 372 G /.737 g $! E.,,,.
7Wo'/0 .37G 7 .1756 / 2912 1.29s2 /. ???:t . G> > 58 .625L .%S_92/9 / . 7 *)4 x C O 7'J/o B 775 7 . 315 G. /.3973 /.2m /.299'/ .6260 .625f 26.9'/25 /.779
- 7'#43 m 3 7G*t 91s 3 g
/.2992 f. 2993_ 1.2993 .G.2 G3 635'l 2 5 . al '((,0 /. 7'l 2 M g
i . KJ/dA . .115 1 . Y 757. 1.2159 /.2?fl_ t.2976 .0 51 .6257 ,25 'l675 /. 7') T ,o , 7'//4f3 175 3 .17 5?. / . p*y/,1 ..J. 2992 /,291/ .6253_ .6253. 2 6 . 3 7'f7 /. ~7 39 S 'g 1 7'4 2 0 /l .3757 ._ J ]SL /.299Q. /.2991 /.29f f_ .635'l .6253 26.9022 f '/ t/O $* )
.1E'f2.d_ allSJ_ mD G6 1.2939 _f,29 7g J a y2_ . 62 st_ _.. 625R 25.???? /.773 Z l 7'O ;h! .S156 .17% 1.M9 : 1.2992 _/29)_ _,f,2 51 . (,2 5'l .25.8/312 4 L_1 *l 'A 7280 _.S767 .715L 09tL /.M93 1.29'12 ._J 2 51 J 258 25 . '/</31 / ?75
'/ ~/.4 0 3_ _J]h.1 __OM_ _/.3'L')2_ f.2993 /.2191
_ s.JGo .6258 16.9567 /. ') ? 7 7'/.9 d 8 825 1 _.R2% . /.2'l93 / 2'r72 .Ja'ltL .62 C,0 .6254 96 .'l967 /,')'l5 f %.23dA ._,Jh3_ i.09yj_ _ /. p'ly7 _.6 ass {
; J]'j]_ !. 9'W 5 .6258 aS.'317l 137G =
I ~//d#4 .1757 115 7 /. 2'11 /.2991 f.2991 .62(. I 6 153 2 G . </s/30 f. ') <l '.t i 4
Notations in this column indicate where changes have been made . d S Table 2. Region 25 PGX Surveillance Specimens Postirradiation Dimensions # 1 and Weight P h o$ NE WEIGitT LENGTH OUTSIDE DIAMETER mb H" PRE POST A PRE I OST A PRE POST A SPECIMEN (g) (g) (%) (in) (in) (%) (in) (in) (%) yO T100A 25.3369 25.1251 -0.84 0.8752 0.8758 0.07 1.2986 1.2992 0.05 y3 L,/ T200A 25.9095 25.6040 -1.18 0.8757 0.8768 0.13 1.2987 1.2991 0.03 x rn T104C 25.3826 25.1818 -0.79 0.8754 0.8763 0.10 1.2991 1.2994 0.02 $@ UE T204C 25.9219 25.7331 -0.73 0.8757 0.8769 0.14 1.2992 1.2994 0.02 g!; T210B 25.9925 25.7096 -1.09 0.8757 0.8765 0.09 1.2993 1.2994 0.01 *5 )> T110B 25.4460 25.2554 -0.75 0.8754 0.8760 0.07 1.2993 1.2995 0.02 O(Q r-T214D 25.9575 25.7067 -0.97 0.8757 0.8761 0.05 1.2988 1.2990 0.02 m > T114D 25.3799 25.1749 -0.81 0.8753 0.8767 0.16 1.2992 1.2992 0.0 -][e $
)4 C)
T120A 25.4022 25.1972 -0.81 0.8757 0.8760 0.03 1.2988 1.2991 0.01 3 m T220A 25.8799 25.6420 -1.07 0.8757 0.8763 0.07 1.2988 1.2993 0.04 3 $ h. T124C 25.4392 25.2404 -0.78 0.8756 0.8775 0. 2 2 1.2992 1.2995 0.02 f h () T224C 25.9431 25.7414 -0.78 0.8757 0.8762 0.06 1.2993 1.2993 0.0 g () T230B 25.9557 25.7433 -0.82 0.8757 0.8762 0.06 1.2993 1.2994 0.01 () T130B 25.4968 25.2898 -0.81 0.8755 0.8762 0.08 1.2993 1.2995 0.02 g T234D 25.8871 25.6657 -0.86 0.8748 0.8751 0.03 1.2987 1.2990 0.02 $ T134D j 25.4430 25.2384 -0.80 0.8758 0.8760 0.02 1.2991 1.2993 0.02 y , Mean 100's -0.80 i .02 +0.09 i .07 +0.02 i .01 -< Mean 200's -0.93 i .16 +0.08 i .04 +0.02 i 01 Mean -0.86 i .13 5 5
^ ~
3ENERAL ATOMIC CO PANY GA-1484
-> TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Doe ment No.
906624 I" A Table 3. Region 25 PGX Specimen Weight Changes Weight Loss (%) CSBBO-3 MEASURED SPECIMEN PREDICTION INITIAL INSPECTION T100A 4.2 0.84 T200A 4.2 1.18 i T104C 4.4 0.79 E
, T204C 4.4 0.73 T210B 4.8 1.09 j T110B 4.8 0.75 5
f T241D T114D 4.1 4.1 0.97 0.81 2 j T120A 4.9 0.81 s T220A 4.9 1.07
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8 T230B 4.3 0.82 g T130B 4.3 0.81 C
'; T234D 4.3 0.86
.E T134D 4.3 0.80 3
Pg 15
. 3ENERAL ATOMIC CO PANY
- GA-1484
+ TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No.
906624 I" A Table 4. Oxidation Remaining in Specimens After i Profiles Cut DEPTH AT END BURNOFF IN OF PROFILE REMAINING SPECIMENS SPECIMEN (mm) (wt %) T100A 1.6 0.41 T200A 1.6 0.23
. T104C 2.3 0.47
] T204C 2.3 0.15 j T210B 2.3 0.19 g T110B 2.3 0.23 j!!
g T214D 2.1 0.12 s T114D 2.0 0.24 5 i T120A 1.2 0.40 i T220A 1.2 0.17 2
.E T124C 2.2 0.12 3 T224C N/A i
a -T230B 1.6 0.08 8 T130B 1.6 0.36 5 e T234D 2.1 -0.18 i T134D 2.2 0.32 5 m i l i i l Page 16 l
1 . Notations in this column indicate where changes have been made g . _4,
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T k f mm O$ ac tn N ew Table 5. Summary of Characterization for Impurities in PGX Sample jQ NO* bj' Impurity (ppm) w m Q@ Z ! Log Ash S Fe Al Da Ca Cu H> Ul Mg Mn l Ni Si V Ti Zn S$H 3 6484-112 Mean 6386 639 3043 225
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. '3ENERAL ATOMIC CC PANY GA-1484
-> TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No.
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, TITLE:
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, TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 2S 80- ] Document No.
906624 I" A - Predicted Profiles 70- p Channel V
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-> TITLE: RESULTS OF PGX GRAPHITE SURVEILLANCE FORT ST VRAIN REGION 25 Document No. 906624 issueA
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