ML20207G887

Destructive Exam of Fort St Vrain Fuel Test Element FTE-2

ML20207G887
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/11/1986
From:	Mccord F, Stansfield O, Turner R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20207G885	List: ML20207G880 ML20207G887
References
908909, NUDOCS 8607230210
Download: ML20207G887 (136)

Text

{{#Wiki_filter:' p Destructive Examination of Fort St. Vrain's Fuel Test Element FTE-2 Prepared by GA Technologies, Inc. for Public Service Company of Colorado Document No. 908909 July 11, 1986 ISSUE N/C Purchase Order No. N-6081 8607230210 860718 PDR ADOCK 05000267 P PDR I

4 GA Technologies Inc. o,. m v., m, ISSUE

SUMMARY

APPROVAL LEVEL DESTRUCTIVE EXAMINATION OF FORT ST. VRAIN DDV&S FUEL TEST ELEMENT FTE-2 O DESIGN DISCIPLINE SYSTEM 00C. TYPE PROJECT I l 00CUMENT NO. ISSUE N0/LTR. N 18 RfE 1900 [ 908909 N/C 4 QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATION s I N/A N/A N/A APPROVAL ISSUE PREP ^ DESCRIPTION / ISSUE DATE FUNDING APPLICABLE BY CWBS NO. ENGINEERING QA PROJECT PROJECT r 0))fg..1;ao N/C JUL 11 M F. McCord O. M. G. P. V. MalakLof Initial Release g y 9/so/T4 CONTINUE ON GA FORM 14851 NEXT INDENTURED DOCUMENTS l Issue Summary il 1 = 7 906771 1 - vil = 120 1 - 120 = 1 (N6081) A-1 = 5 B B-5 = l Total 134 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 PAGE il 0F 134

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELDENT FTE-2 ISSUE N/C TABLE OF CONTENIS N PAGE NUMBER 'T 1.0 SURRY AND CONCLUSIDNS 1

2.0 INTRODUCTION

4 3.0 ELEENT DESCRIPTION............... 7 31 Graphite Block............... 7 32 Elanent Assembly.............. 8 4.0 IRRADIATION HISTORY............... 10 5.0 VISUL EXAMINATION 11 6.0 DISASSDELY OF IliE ELEENT 12 6.1 Drilling the Bottan 12 6.2 Renwal of the Top Slab 13 6.3 Fuel and Monitor Crucible Renwal 13 i 6.3.1 Redrilling the Back of the Elanent.. 14 6.3 2 Fuel anc Monitor Crucible Renwal by the Motte Driven Pushing Device... 15 l 6.3.3 Fuel ard Monitor Crucible Renwal via i

s Hydraulic Press..........

16 l l 6.3.4 Cutting the Elanent for Fuel and Monitor Crucible Renwal 16 i l 6.4 Penwal of Graphite Sanples 17 7.0 EXAMINATION AND EVEUATION 18 g l 7.1 Visual Appearance of Fuel Rods....... 18 O _ _

i TITLE: DESTRUCTIVE EXAMINATION OF FURT D0C. No. 908909 ST. VRAIN FUEL TEST ELDENT FTE-2 ISSUE N/C TABLE OF CONTENIS PAGE NUMBER Q 7.2 FSV Reference Fuel Metallographic Examination 19 7.2.1 Meta 11ographic Results of Fuel Rod Matrix.............. 19 7.2.2 Meta 11ographic Results of the Fuel Particlas............ 20 73 Monitor Evaluation 25 7.3.1 Visual Examination of Monitor Crucible 25 732 Discussion of Monitor Crucible Observ ations............. 26 s 7.3 3 Monitor Analysis and Results..... 28 7.4 Graphite Analysis and Evaluation 29 7.4.1 Material............... 30 7 4.2 Test Methods............. 31 7 4.3 Results 32 8.0 ACKNCWLEDGEENIS 35 i 90 REFERENCES 36 l l TABLES 39 FIGURE 3 68 APPENDIX A A-1 APPENDIX B B-1 l 0._

TITLE: DESTRUCTIVE EXAMINATION OF FDRT 00C. NO. 908909 ST. VRAIN F1JEL TEST ELEMENT FTE-2 ISSUE N/C LIST OF TABLES PAGE NUMBER Y 1. Test Data and Obj ectives............... 39 2. Dimension Specifications............... 40 3. Fuel Accountability of FTE-2 at the End of Cycle 3.. 41 4. Pushout Forces.................... 48 5. Measured FTE-2 Fuel Rod Macroporosity 55 6. Meta 11ography Results 56 7. Coated Particle Attributes of FSV Fuel Test Elment Burnup Saples.................... 57 8. Neutron Fluence Monitors............... 58 9. Monitor Results 59 10. Test Specimens Machined fra Test Elment FTE-2... 60 11. Tensile Properties of Irradiated H-451 Graphite fra FTE-2 (Axial Orientation) 61 12. Tensile Properties of Irradiated H-451 Graphite fra FTE-2 (Transverse Orientation)......... 63 13. Swinary of the Tensile Properties of Cou;cn Specimens of H-451 Graphite frm Fort St. Vrain Test Elment FTE-2 66 14. Thermal Expansivity (25-5000C) of Coupon Specimens fra Fort St. Vain Fuel Test Elment FTE-2 (H-451 Graphite) 67 >O w - 111 -

TIILE: DESTRUCTIVE EXAMINATION OF FURT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTE-2 ISSUE N/C LIST OF FIGURES D 4 PAGE NUMBER 1. Standard FSV Fuel Elment Configuration .......68 2. FTE-2 Side Face Identification Data.......... 69 3 Fbel Rod Configuration for Cure-in-Place Assembly Process........................ 70 4. Description of Test Arrays in FTE-2.......... 71 5. Schmatic Diagra of Monitors Used in F3V Fuel Test El m e nt........................ 72 6. Radial Position of Monitor Crucibles 73 7. Core Positions (Layer 6) Showing Location of Eight Test El ments..................... 74 8. Side Face A (Taken at HSF at FSV)........... 75 9. Side Face B (Taken at HSF at F3V)........... 76

10. Side Face C (Taken at HSF at F3V)........... 77

11. Side Face D (Taken at HSF at F3V)........... 78

12. Side Face E (Taken at HSF at FSV)........... 79 13 Side Face F (Taken at HSF at FSV)........... 80 l

14. Stains on Top Surface 81

15. Hot Cell Work Stations 82 0

16. First cut frm FTE-2 83

17. Monitor Crucible and Fuel Assembly for 4 Monitor Crucibl e S ta cks....................

84

18. Side Face C Dunaged by Hydraulic Press (note fuel particles frm crushed rods)........ 85

- iv -

~ TITLE: DESTRUCTIVE EXAMINATION OF FORT 00C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTE-2 ISSUE N/C LIST OF FIGURES N PAGE NUMBER

19. Bonding fra CIP Rod Curing at Axial Location Approximately 8 Inches fra the Top of the Elment 86

20. Location of Test Slab in Fuel Test Elment......

87

21. Typical Appearar.ce of the CIT and CIB Rods......

88

22. Typical CIP Stack 89

23. Fuel Rod Used in Meta 11ography (FSV reference fuel:

(Th, U)C2 TRISO and ThC2 TRISO)............ 90

24. Photmicrographs Representative of Matrix Phase of Irradiated Rod 13 fra Stack 44 91

25. Representative Photmicrographs of Caposite of Radial Cross Section of Fuel Rod 13, Stack 44 (left side of rod) 92 26.

Photmicrographs of Typical Fissile (a,b) and Fertile (c) Particles. (a) and (c) are Bright Field Illtainated and (b) is under Polarized Light.. 95

27. Photmicrographs of Typical Fissile (a,b) and Fertile Particles.

(a,b,c) are Bright Field Illtainated and (b) is under Polarized Light........... 96 28. Cracked (Th,U)C2 Kernel 97

29. N o (Th,U)C2 Fuel Kernels Exhibiting Localized Swollen Areas.

(a,c) are Bright Field Illtainated and (b) is Under Polarized Light........... 98

30. Typical Buffer Debonding in the Fissile (a) and

(# Fertile (b) Particles 99

31. Buffer Cracking in the Fertile Particle 100

-y_

TITLE: DESTRUCTIVE EXAMINATION OF FDRT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C LIST OF FIGURES

• \\

PAGE NUMBER S

32. Debonding (a) of IPyC and Failure (b) of the IPyC and sic Coatings 101

33. Failure of the IPyC and sic Coatings Resulting frm Densification of the Buffer.

(See also Fig. 29)... 102

34. Typical Lenticular Flaws in the sic Coating of a Fertile (a) and Fissile (b) Particle.........

103

35. Fissile Particles with Heavy Metal Dispersion Shwing Chanical Degradation of the IPyC and sic Coatings

....................104

36. Top Monitor Crucibles fra Holes 67 (a,b) and 18 (c,d) Show Cracking.

The Cap Was Cut in the Monitor fra Hole 18, but the Monitoring Devices were Oseable..................... 105

37. Top Monitor Crucible fran Hole 307 Shwing Cracking.

This Monitor Crucible was Located Under a Dowel.... 106

38. Top Monitor Crucible of Hole 86 (4 monitor crucible stack) Showing Cracking.....

107

39. Cracking in Second Monitor Crucible fran Top of Hole 248

...................108 i

40. Cracking in Third Monitor Crucible frm Top of Hole 248

......................109

41. Cracking in Third Monitor Crucible frcr4 Top of Hole 86 110

42. Meta 11ographic Mount (a) Shows the Ur. irradiated O

and in-situ Nb-15 Zr Tubes; (b) and (c) Show an Enlarged Section of Each, Respectively. Note the Swelling in the Irradiated in-situ Tube Section (c).. 111 er

43. Unirradiated (a) and Irradiated in-situ (b) Niobiun Alloy Tubes fra Monitor #1 of Hole 248........

112 - v1 -

TITLE: DESTRUCTIVE EXAMINATION OF FURT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FIE-2 ISSUE N/C LIST OF FIGURES 3 PAGE NUMBER 4

44. Location of Specimen Cores in Face A 113

45. Location of Specimen Cores in Face B 114

46. Location of Specimen Cores in Face E 115

47. Location of Specimen Cores in Face F 116

48. Tensile Strength of H-451 Graphite fra Fuel Test Elment FTE-2 for Different Faces of the Block..

117

49. Young's Modulus of H-451 Graphite fra Fuel Test Elment FTE-2 for Different Faces of the Block..

118

50. Tensile Fracture Strain of H-451 Graphite fra Fuel Test Elment FTE-2 for Different Faces of the Block..

119

51. 7hennal Expansivity of H-451 Graphite fra Fuel Test Elment FTE-2 for Different Faces of the Block..

120 0 - vii - --.-_.-.~,_.__.----r_. -.. _,... -. - - -... ~.... - _. _. - - _ _. _. -.. -.,..., _. -.. -.., -, -.. - - - -. - -... - - - - -.. - - - -..

_. = 4 1 TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN RJEL TEST ELEENT FTE-2 ISSUE N/C 1.0 SUNIARY AND CONG.USIONS e Eight fuel test elenents were inserted into the F3V core in March )N and April 1979 FTE-2 was one of those test eleents. It was irradi-ated for 483 EFPD in core location 22.06.F.06 where it experienced a calculated average fast neutron fluence of 1.9 x 1025 n/m2 E> e I 29 fJ)HIGR, time and voltme averaged graphite and fuel temperatures of 5100C and 7000C, and fissile and fertile FIMAs of 45% and 0.9%, respectively. FTE-2 was the second test element to be examined non-destructively at F3V, and the first test elenent slated for destruc-f tive examination. It arrived at the GA Hot Cell on January 20, 1986 for this examination. lhe destructive examination was to verify the performance of the eleent by acquiring and evaluating the in-pile data on the H-451 l graphite block and the FSV reference fuel. The observations and results of the destructive examination are stanmarized belm. ] I 1. The H-451 graphite block was in excellent condition. No cracks were observed on any of the surfaces. All observed l marks and blanishes were surface markings and did not hann l the graphite body. 2. The measured H-451 graphite properties of tensile strength, t Young's

Modulus, tensile fracture

strain, and thermal l

expansivity showed no systematic variation fran face to face i of the hexagonal block. !lO \\ tn I l ! I

TITLE: DESTRUCTIVE EXAMINATION OF FORT 00C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C 3. The measured tensile strengths were in good agrement with the values given in the Graphite Design Data Manual (Ref. 15). The Young's moduli fell at the low end of the band predicted by the Graphite Design Data Manual, but there was no significant inconsistency. 4. The measured thermal expansivities average about 19% lower than the predicted values. This difference could have been due to the actual graphite temperature being higher than calculated or to an error in the design polynmial used to calculate changes in thermal expansivity. Experimental verification of the graphite temperature by analysis of the silicon carbide temperature monitors would help to determine the cause of the inconsistency. This analysis is underway. If the current design polyneial overpredicts the graphite l thermal expansivity, the design polyneial would generally be conservative with respect to graphite stresses. 5. There was evidence (high pushout force) of mechanical inter-action between the cure-in-place fuel rods and the graphite body. This interaction was greater near the upper fourth of the elment. There were no observed cracks in the fuel holes of the block fra this interaction. It should be noted that there are no plans to use CIP as a F3V reference curing process. 6. There was evidence of mechanical interaction between the g moniter crucibles and the fuel holes. All of the monitor crucibles were cracked and were difficult to renove. There a were no observed cracks in the fuel holes of the block fra this interaction. TITLE: DETRUCTIVE EXAMINATION OF FORT DOC. NO. 908909 ST. VRAIN FUEL TEST ELDENT PTE-2 ISSUE N/C i 7. The cured-ir> tube and cured-ir> bed fuel rods were in l T excellent condition. They were pushed out manually with l little effort. The cure-ir> place rods were in good to fair ] N condition. There was considerable fuel rod-gra#11te bo$ 4 ) mechanical interaction. Fuel rod rewal was acocuplished by l using a motor driven pushing device and/or Wdraulic press tait or cutting. The CIP fuel rods reoved at forces below 500 lbs were in good cordition. The CIP fuel rods reoved at i greater than 500 lbs of force were in fair condition. These fuel rods tended to be more susceptible to particle debonding j and rod fractures. ] 8. The graphite monitor crucibles were in fair to poor condition. All of the monitor crucibles were swollen and cracked. The niobita alloy (Nb-15 Zr) tubes inside of the j graphite crucible enlarged. The cause of the swelling has ) not been identified, but water ingress into the core during i service mg have introduced oxygen and hydrogen which react t with the niobita. 9. The F3V reference fuel ((Th,U)C2 TRISO and ThC2 TRISO) was in excellent condition. The average measured macroporosity was 235. The matrix was judged to be in excellent condition i after irradiation. There was no matrix-particle interaction i l observed. i 1'

10. A total of 275 fissile particles and 184 fertile particles fo were examined.

For the (Th, U)C2 1RISO and ThC2 R ISO j particies, respectively, the sic conting failure was 0 75 and l, 0.5%; the IPyC failure 1.15 and 1.15. 1here were no OPyC l failures in either particle types. 1 1 TITLE: DESTRUCTIVE EXAMINATION OF FURT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTE-2 ISSUE N/C

11. There was no observed kernel migration with the deposition of 3

carbon behind the kernels. Wo (Th,U)C2 kernels exhibited localized swollen areas which extruded into cracked buffer 4 coatings with one causing failure of the IPyC and sic coat-ings. This phenmena has been observed in other experiments (Refs.12 and 13).

12. The cheical behavior of the TRISO particles was acceptable.

There were no observed signs of cheical degradation of coat-ings in the fertile particles. No fissile particles had fuel dispersed throughout the buffer and IPyC coatings. In one of the particles, the cheical interaction had completely degraded the IPyC in one spot and had begun degrading the sic coating up to about 4Am. There was less observed fuel dis-persion and cheical degradation of coatings in the F3V segment 7 quality fuel of FTE-2 than in the initial core loading fuel of FEV elment 1-2415 (Ref.14). The performance of FTE-2 was compared with expected perform-ance and judged to be very good. The FSV reference fuel was in very good condition after being irradiated for cycles 2 and 3. The H-451 graphite was in excellent condition, its performance was judged to be very good.

2.0 INTRODUCTION

Eight fuel test elments (FTEs) were inserted into the core of the high taperature gas-cooled reactor (HIUR) at the Fort St. Vrain (FSV) Nuclear Generation Station site during the first refueling in March -4

TITLE: DESTRUCTIVE EXAMINATION OF FURT 00C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C and April 1979. The fuel test elenents were designed to operate i within the limits of peak fuel temperature, neutron fluence, and fuel burnup specified for the initial core and reload fuel elenents. R>ni-tors were included in the test elenents to measure each of these paraneters. Locations of the elanents within the core were selected to yield test results over a range of exposure conditions. One test elenent was located in each of sepents 2 through 6, and three test elenents were placed in sepent 7. The fuel test elanents were designed to the same envelope dimen-sions and structural criteria as the standard FSV fuel elenents. The test elenents were fabricated fran near isotropic H-451 grade graphite instead of the needle-coke H-327 grade gra;hite used in the initial core elenents. Elanents fabricated fran H-451 grade graphite are designated for FSV refueling sepents and advanced HIGR designs. Other differences between the test elenents and regular elenents are in fuel materials, assembly and curing process, and in the use of test arrays and monitors. The fuel test elanents are designed to demon-strate the integrity of advanced fuels and core materials in a representative HIGR neutron spectrun and heliun coolant environnent. Examination of the test elenents began with the examination of FTE-1 at the F3V Hot Service Facility (HSF) during the nondestructive l examination of core sepent 2 in March 1981 (Ref. 1 ). The second l fuel test elenent to be examined was FTE-2. FTE-2 was examined non-i destructively in June 1984 at the FSV HSF during the examination of 62 l fuel and reflector elenents fran core sepent 3 (Ref. 2). FTE-2 was the first of the fuel test elanents slated for destructive exami- ) o nation. Therefore, it was shipped to the Hot Cell at GA Technologies for these examinations. l l 1 __ __ __ - - -_.

TULE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909' ST. VRAIN FUEL TEST ELEIENT FTE-2 ISSUE N/C This report covers the results of the destructive examination and i evaluations perforned upon FTE-2. The examination and evaluations included the following tasks: o drilling through the fuel holes on the botta of the block o reoving the fuel plugs by sawing off the top of the fuel elment o removing the fuel stacks o measuring the fuel stack pushout force on 10 stacks o relocating the fuel into a receptacle block o removing the side faces fra the block o collecting the graphite axial and transverse cores for material property tests o reoving the monitors o perfornir.g analyses of 6 monitors o perforuing analyses of the graphite cores The purpose of this destructive examination was to provide l experimental data on the irradiated elenent, to verify its perforn-n i ance, and to acquire in-pile data on the graphite and fuel. Coupon 9 6-

TITLE: DESTRUCTIVE EXAMINATION OF FORT 00C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C specimens cored fra the irradiated H-451 grade graphite block pro.- S vided medianical and therinal property data to validate models and assunptions used in licensing the use of H-451 graphite in the F3V core. Metallography of a F3V reference fuel rod provided data on integrity and perforinance of the fuel. Fluence and FIMA (burnup) monitors provided data to aid in assunptions. Specific objectives of the destructive examination are given in Table 1. 3.0 ELEENT DESCRIPTION 31 Granhite Block The fuel test elenent graphite blocks were manufactured fra H-451 grade graphite developnent lot 426. i+-451 graphite is an extruded near-isotropic petroleun-coke graphite produced in logs. j Regular F3V fuel blocks in sepents 1 through 8 and part of sepent 9 were fabricated fra needle-coke H-3W graphite. Sepent 10 and beyond will be fabricated fra H-451 graphite. H-451 graphite is more isotropic than H-327 graphite in strength, elastic modulus, and thermal expansivity. Also, the absolute strength of H-451 is higher than that of H-327. The advantage of H-451 graphite over H-3U is attributed to differences between the properties of the fillers used in the manufacture of the graphite. A near-isotropic petroleun-coke filler is used in the manufacture of H-451 and a needle-coke filler is used in the H-327 grade. o 4 -_

~ i s 1 TITLE: DESTRUCTIVE EXAMINATION OF FORT > D0C. NO. 908909 ST. VRAIN F1JEL TEST ELEENT FTE-2 ISSUE N/C FTE-2 was fabric ted fra a H-451 graphite log into a hexagonal s cross section with dimensions of 360m (14.172 i 0.010 in.) across flats by 793ns (31.22 + 0.04/-0.02 in.) high. The elanent consisted 5 of a standard fuel body having 210 fuel holes, 6 burnable poison holes, and 108 coolant channels (see Figure 1). The machining speci-fication (Ref. 3) for the block was designed to control the gaps between the fuel rods and fuel holes as presented in Table 2. The specifications account for green rod shrinkage and the effects of cured-in-place (CIP), a.stecial process for carbonizing the fuel rod matrix. All machining was done by Camissariat a L'Energie Atmique (CEA, Saclay, France). The block was tmiquely identified by a serial ntaber (8-020" FTE ntaber (FTE-2), assembly type ntaber (206) and core locath. (22.06.F.06). These data were' engraved on the identification face of the block (Fig. 2 ). 32 Element Assembly The FSV reference rod curing process is the cured-in-bed (CIB), a method of carbonizing green fuel rods in packed altnina powder beds and then after renoval fra the altaina and a high taoperature heat treatment inserting the carbonized rods into the block. The FSV fuel rod examined in section 7.2 was processed with the CIB technique. However, in FTE-2 over 92% of the fuel rods were cured-ird place (CIP). 1he CIP process is a method of curing the green rods in the block by heating to 18000C to outgas and carbonize the matrix. Axial gaps o between fuel rods are controlled by the insertion of plastic spacers TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. No. 908909 ST. VRAIN FlJEL TEST ELEMENT FTE-2 ISSUE N/C which volatilize during the heat treatment. De CIP assembly is shmn in Fig. 3. De remaining FTE-2 fuel rods used the reference CIB process or were cured-in-tube (CIT). In the CIT process, green rods S are cured in alunina tubes, pushed out to fonn locM carbonized rods, and then inserted into the elment. A regular F3V fuel elment contains 210 fuel holes which house 3132 fuel rods. Hwever, in FTE-2 monitoring devicas replaced 22 fuel rods. De remaining 3110 fuel rods in FTE-2 were fra seven different fuel varieties and consisted of driver fuel (UC2 IRIS 05, 202 TRIS 0) and experimental fuel contained in 6 test arrays (test array 7 also contained UC2 TRISO and Th02 TRISO driver fuel). The test arrays and fuel varieties are shwn in Fig. 4. FTE-2 also included 36 monitor packages. Each is a 0.97 inch (24.6 mm) long H-451 graphite crucible containing a silicon carbide rod, dosimetry wires sealed in niobita tubes, and UC2 and ThC2 fuel particles to monitor ta perature,

fluence, and fuel

burnup, respectively.

Manufacture of these monitors is described in. Ref. 4. De design is dimn in Fig. 5. Sufficient monitors are located across the block to allw measurenent of intra-block taperature and fluence tilts. One stack in each of the seven test arrays contains four monitors distributed as shmn in Fig. 6. Because of the high firing temperatures (18000C) required during rod curing, the monitors were assembled after the curing process with loose rods that were l cured-in-tube or cured-in-bed. l 0 "TRISO - refers to a four-layer composite coating consisting of an inner buffer layer and an outer composite structural coating of sic sandwiched between two layers of pyrolytic carbon. '

TIT E: DESTRUCTIVE EXAMINATION OF FORT DOC. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C 4.0 IRRADIATION HISTORY s FTE-2, serial number 8-0206, was irradiated in the F3V reactor s core in region 22, column 6, and core layer 6 (third active layer frcan the top of the core). This location was chosen to avoid rodded regions and regions near the reflector to minimize fuel block stresses caused by temperature and fluence gradients. The core position is shwn in Fig. 7 The elment was irradiated in this core location for cycles 2 and 3. The elment accunulated a total of 483 effective full power days (EFPD'). The average integrated calculated fast fluence acetanulated by the elanent was 1.9x1025n/m2 (E>29fJ)HIGR (Ref. I 5). The calculated time and volune-averaged graphite temperature was 510oC (Ref. 2). The fuel accountability and elanent burnup are shwn in Table 3 (Ref. 6). 'An EFPD is the equivalent of 1 day of operation at full power (842 W). l \\ i O . l

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C 5.0 VISUAL EXAMINATION s A visual inspection was conducted to confinn and/or supplanent the visual inspection perfenned in the HSF at F3V (Ref. 2). he elenent s was placed in a vertical position by suspending it with a grapple through the handling hole. Each side face was then observed by manually rotating the elenent. Observations were made via the Kollmcrgan perioscope and the hot cell's viewing windows. he Kollmcrgan periscope allowed enlargement (up to 10X) and photography of the observations. FTE-2 was in excellent condition. There were no new scratches or blanishes fran the handling and transport of the elenent, he side faces had insignificant anall scratches and scrapes which were observed during the surveillance at FSV (Ref. 2). Figures 8 through 13 show the side faces. Bere was a discontinuous vertical scratch rtmning nearly the length of face C. We upper right side of face F had vertical scratches on the left side. Similar markings have been seen on the regular F3V elenents and are believed to have been caused during handling and storage. The bottan and top surfaces were in excellent condition. The bottan surface was relatively free of blanishes. The top surface had a few dark markings located around fuel holes, coolant and adjacent burnable poison holes (Figure 14). Similar markings were observed on l FTE-1 where it was denonstrated that the marks were not built up of substances, but stains probably caused by the CIP outgassing fran pitch in fuel rod matrix since none of the regulsr PSV elenents had this type of staining (Ref. 7). ~. - -

l TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN RIEL TEST EEMENT FTE-2 ISSUE N/C 6.0 DISASSEELY OF THE ELEENT s The disassembly of FTFe2 was carried out in the high level hot s cell. The work stations are laid out in Fig.15. The requirements of the test procedure (Ref. 8) were actiered to as closely as possible.

However, FTE-2 was the first cured-in-place elenent to undergo disassembly and therefore presented mag unique problens which resulted in deviations fran the procedure. All deviations were agreed upon by a Quality Assurance representative, the cognizant engineer and project management.

The deviations will be noted in the appropriate sections. The disassembly of the elenent is described below. 6.1 Drillina the Bottom To push fuel from the bottan of the elenent, a specialized drilling device was used to remove the graphite webs on the botta of the blind fuel holes. The drill was positioned and aligned using the coolant holes as guides. Six slots on the device pennitted the six fuel holes surrounding a coolant hole to be drilled without relocating the device. The fuel holes were drilled to a depth of 0.25 inch (6 m) and a diameter of 0.375 inch (9 m). Reference 8 specified this depth, but the drill did not pierce the conical tip of some fuel holes. The graphite thickness between the bottom of the elanent and the bottan of the conical tip of the fuel holes varied. Therefore, after several depth settings, the drill was set to a depth of 0.625 inch (16 nun). 1his allowed enough clearance in the fuel holes to insert a pushred I l l

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN RJEL TEST ELEMENT FTE-2 ISSUE N/C and push the fuel. The depth setting for the fuel holes located under the dowels was changed frm 1.29 inch (33 m) to 1.67 inch (42 m), also. s 6.2 Rannval of the Too Slab A modified band saw was placed in the high level hot cell to clap and hold down a FSV-type el ment in a cradle during cutting operations. This saw was used to do all of the cutting of the irradiated elment. A vacum cleaner was placed in the high level hot cell to clean up all the debris generated during the cutting. A 0.5 inch slab was cut off the top of the elment. Reoval of the slab bared the fuel in the holes which were not located under the dowels. The reoved slab contained the fuel plugs and about 0.12 in. (3 m) of the tops of fuel rods and top monitor caps (Fig.16). The fuel stacks did not slip down during volatilization of the spacers during the CIP nor did they slip down during the cooling and gap fonnation between rod and hole. The blade of the saw was dulled by the cutting and was replaced. 6.3 Fuel and Monitor Crucible Removal Fig. 15 shows the fuel rod pushing and storing operathns. An unirradiated grapnite block (S/N: 1-1975) served as a receptacle block for the fuel fra FTE-2. All unused fuel (CEA, ORNL, and GA fuel) was placed in this storage block for disposal. l o i Fuel fra 10 CIB and CIT stacks without monitors were reoved frm FTE-2 by pushing the fra the back of the elment into a dual receiv-a ing trough attached to the front of the elment. A force gauge was ! j

4 TITLE: ' DESTRUCTIVE EXAMINATION OF FURT D0C. NO. 908909 ST. VRAIN RJEL TEST ELDENT FTE-2 ISSUE N/C used to measure the initial force needed to move the fuel for a few stacks. A 34.0 inch (864 m) long push rod with a 0.375 inch (9.5 m) dianeter was used to push the fuel into the receiving trough. he rods were transferred via the trough to the receptacle block. The CIT and CIB stacks without monitors offered little or no j resistance to pushing (see Table 4). However, CIT and CIB stacks with l monitors would not push. We fuel rods and monitors were assembled into the fuel hole after the curing process (Fig.17). he naminal dianeters of a fuel hole, monitor crucible and fuel rod were 0.498 inch (12.6 m), 0.489 inch (12.4 m), and 0.492 inch (12.5 m), respectively. Berefore, the initial rod and monitor clearances inside the fuel hole were sufficient. Since the fuel in other CIB and CIT stacks pushed out easily and the initial clearances inside the l hole were sufficient, the monitors were judged to be causing the fuel I renoval problens. (This is discussed in more details in Section 7 3). Manual pushing on the CIP fuel stacks did not move the fuel. A slide hammer was fr.bricated to jar loose the rods. Manual pushing on the stacks after hamering did not move the fuel. P 6.3.1 ram 111nn tha u of tha n-nant Other means of fuel renoval were investigated since manual pushing did not work. A motor driven rack and pinion pushing device, used on FSV 1-0743 (Ref. 9), was refurbished. he device has a push rod slightly under 0.5 inch (12.7 m) in dianeter. Se blind holes on the bottcan of FTE-2 were originally drilled to 0.375 inch (9 5 m), therefore the holes were redrilled to a dianeter-of 0.5 inch.

TITLE: DESTRUCTIVE EXAMINATIbN OF FORT D0C. N0'. 908909 ST. VRAIN FUEL TEST ELENENT FTE-2 ISSUE N/C 6.3.2 Fuel and Monitor crucible Ramnval by the Motor Driven Pushina Device Ee pushing device rests on a movable bar which permits manual movanent fra left to right up to 9 fuel and coolant holes fra an edge and vertical movenent up to 5 rows. ne elenent is lifted and manually rotated so that other areas are accessible to the push rod. De pushing device is also equipped with a 500 lb. capacity force gauge for measuring the force applied to initiate and sustain movanent. Fuel stacks were renoved by pushing fra the bottom or top of the elenent using the motorized pushing device. As fuel was pushed out, it was placed in a pan then transferred to the receptacle block. A total of 56 stacks, located one or two rows fra the side face edges, was renoved with the pushing device at forces up to 500 lbs. Another 68 stacks were removed at forces in excess of 500 lbs. Of the 124 CIP stacks renoved, 6 stacks had 1 top monitor each which was cracked (see Section 7 3). A total of 76 stacks resisted renoval with the pushing device. In most cases the first ten to twelve fuel rods in each of the renaining 69 CIP stacks moved, but stopped after breaking through the sixth gap left by the volatile spacers (see Fig. 3). Even pushing fra the top did not break loose these rods. In the other 7 renaining CIB and CIT sta cks, there was little or no movenent by pushing fra either the bottom or top of the elenent. Each of these stacks contained 4 monitors.

TITLE: DESTRUCTIVE EXAMINATION OF FORT DOC. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTF-2 ISSUE N/C 6.3.3 Fuel and Monitor Crucible Ramnval via a Hydraulic Press l A hydraulic press was fabricated to try to renove the remaining 76 stacks. The dianeter of the ran was 0.497 inch (12.6 an). Wo 34 inch (864 un) long rods which fit into coolant holes served as guides. The tmit was tried at forces up to 1700 lbs, the piston went in about an inch, but stopped. Another stack was tried. More force was applied, and at 2300 lbs a chip broke off the block and two fuel rods were crushed (see Fig. 18). Renoval via the hydraulic press was abandoned at this point. 6.3 4 Cuttina the Elamant for Fuel and Monitor Crucible Ramnval The lower three-quarters of each of the 69 renaining CIP stacks pushed. Consequently, the elenent was cut in half to remove the fuel by pushing with either the motor driven pushing device or the hydrat>- lic press tmit. During this cutting the blade was dulled, but no change in blade was needed. All of the CIP stacks in the bottan half of the elenent were renoved by pushing with either the motor driven pushing device or hydraulic press tmit. Pushing on the CIB and CIT stacks with monitors produced no movanent. However, in a few of these stacks after the cutting of the elenent, a few of the rods which did not have monitors blocking movanent were loose and slipped out. It was concluded that i the monitors were swollen and should be cut out. All of the monitors and embedded fuel rods were cut out of the bottan half of the elenent. All of the monitors were cracked and wedged tightly into the fuel holes. See Section 7.3 for more details on conditions of the monitors.

TITLE: DES 11tUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUE TEST EEENT FTE-2 ISSUE N/C Fuel stacks in the top half of the elment were pushed upon by the various pushing devices, but the fuel resisted eming out. Therefore, the top section was cut in half. The block was cut at an axial location which showed bonding of the rods at several holes (see Fig. o i 19). The free of the pushing unit could not support the shcrter sections. Therefore, the hydraulic press unit was used to push the stacks out. Sixty-six fuel stack sections were pushed out of the lower cut section of the top. Ihree fuel stacks and 7 stacks with monitors were cut out. All of the CIP stacks in the upper section pushed out, but the 7 stacks with monitors were cut out. 6.4 Removal of Granhite %mnles The side faces were reoved before the elment was cut (Section 6.3.4). Seven inch (178 m) slabs were reoved fra side faces A, B, E and F of FTE-2 as shown in Fig. 20. Axial and transverse cores and buttons were cored fra the 7-inch slabs as shown in Figures 44 through 47. Saples were not taken fra side faces C and D. Side face C was damaged (see Section 6.3.3), and side face D was needed for aligning during the cutting. Entire side faces were cut fra the elment instead of the 7 inch block section as required in Ref. 8. This was done so that the graphite studies could proceed without waiting for the completion of the fuel and monitor reoval. The cores were made using a drill press and coring drills. The approximate drill speed was 1850 RPM. The axial and transverse cores were 0.27 inch (7 m) P dimeter and 4 inches (102 m) long. The t buttons were 0.4 inches (10 m) in dimeter. These samples were e delivered to the graphite laboratory for mechanical and thermal studies (see Section 7.4).

TIH.E: DESTRUCIlVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FljEL TEST ELEMENT FTE-2 ISSUE N/C 7.0 EXAMINATION AND EVALUATION Results of examinations and evaluations of the fuel, monitors, and graphite follow. 7.1 Visumi Accearance of' Fuel Rods The fuel rods frcm the CIB (FSV reference fuel) and CIT stacks were in excellent condition. The rods maintained their structural integrity. Surface debonding, end cap damage, chips and nicks were very minimal. Fig. 21 shows typical CIT and CIB fuel rod appearance. The fuel rod graphite interaction was minimal for the CIT and CIB stacks. The rods were manually pushed out with little effort (see Section 6.3). ine fuel rods frcm the CIP stacks were in good to fair condition even though there was considerable fuel rod-graphite interaction as evidenced by the high push out forces (see Table 4). Groups of two fuel rods fused together during curing making one ~3.9 inch (98.6 m) long rod. The CIP fuel rods removed using less than 500 lbs of force had minimal structural damage. Their appearance was similar to the CIT and CIB fuel rods. Fig. 22 shows a typical CIP stack. CIP fuel rods removed with greater than 500 lbs tended to be more susceptible to particle debonding and rod fractures. TWo fuel rods were crushed at forces greater than 1700 lba during an attempt at fuel rod removal via the hydraulic press unit (see Section 6.3 3 and Fig. 18). Forces of this magnitude were abandoned. The rods could main-tain structural integrity at up to a push force of 1500 lbs...

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTE-2 ISSUE N/C 72 FSV Ref'erence Fuel Metallogranhic Evamination e Meta 11ographic examination was performed on one fuel rod fran FTE-2 which contained FSV type fuel. The ceramographic examination 6 was performed to observe the temperature and irradiation induced changes in the condition of the fuel rod matrix, fuel kernel micro-structure, and fuel particle coatings. Fuel rod 13 of stack 44 fran test array 1 was selected for the metallographic examination (Fig.23). This fuel rod contained F3V reference thoriun-uraniun carbide TRISO fissile particles and thoriun carbide TRISO fertile particles fran core segnent 7 production. The axial location of the rod 13 was selected because it was expected to have experienced a higher tanperature and fast neutron flux history relative to other locations, and thus would provide earlier indications of these effects in the fuel. The fuel rod was mounted lengthwise in resin, cut, ground, and polished. The polished section was passivated with a 50/50 aqueous solution of nitric acid to decrease the rate of hydrolysis of the exposed thoriun carbide kernels. The entire polished surface was then examined under bright field 111unination and/or polarized light with a Leitz metallograph. 7 2.1 Metallogranhic Results of Fuel Rod Matrix The carbonaceous fuel rod matrix was judged to be in excellent condition after irradiation. The integrity of the bonded fuel rod was excellent. No matrix spalling, particle debonding, matrix cracking, nor any observable hannful tenperature or irradiation effects were

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELE)ENT FTE-2 ISSUE N/C seen in the examined fuel rod. No matrix-particle coating interaction was seen. The irradiated microstructure was similar to the observed microstructures in FSV segnent 2 elenent S/N: 1-2415 and in the FSV fuel irradiated capsule F-30 (Refs. 14 and 12). Representative s photanicrographs of the matrix graphite are shown in Fig. 24. Matrix macroporosity is a measure of the voids in the matrix of fired rods. Voids of interest are characterized by an absence of continuous matrix with a dimension in excess of 50 microns. Matrix macroporosity affects the anount of surface area available for bonding between the fuel particles and the matrix. Thus, the matrix macro-porosity is related to the strength and thennal conductivity of the fuel rod. Fuel rod matrix macroporosity was measured by the point-cotmt method (Appendix A) fran five 30X magnification dianetral ecm-posite ceramographic cross-sections (Fig. 25). Table 5 presents these measured macroporosities. The average measured macroporosity of 23% is consistent with the results of the F-30 fuel proof-test capsule l (Ref. 12). Me m11oaranhic Ramn1ts of the Fuel Particles 7 2.2 r In the TRISO particle design, the fuel kernel is surrounded by a low-density, porous pyrolytic carbon buffer layer which provides a void volune to accommodate fission gases and kernel swelling, and attenuates fission product recoils. A coating of silicon carbide l (sic) is sanckiched between the inner and outer coatings of high-density pyrolytic carbon (IPyC and OPyC) which provide a composite pressure vessel to retain gaseous fission products. The sic coating provides a barrier against the diffusion of metallic fission products

1 TITLE: DESTRUCTIVE EXAMINATION OF FURT DOC. NO. 908909 ST. VRAINJUEL TEST EL9ENT FTEM ISSUE N/C I and increases the mechanical and dimensional stability of the particle during irradiation. The high density IPyC and OPyC coatings protect and provide mechanical support for the sic coating. During irradi-ation tensile stresses in the PyC coatings he to irradiation-in&ced densification help mairtain the sic coating in compression. There-4 fore, coating failure resulting fra mechanical interactions can occur as stresses are generated in the composite coatings as a result of irradiated-induced density or dimension changes and other irradiation and/or temperature effects. Qianical degradation of coatings is also a potential failure mechanian in irradiated fuel particles. Migrating kernels, dispersed fuel, fission products or contaminants can cause chemical reactions with coatings. These types of chemical interactions can cause coating degradation and breaches in the integrity of the coatings. 9 A total of 275 fissile particles and 184 fertile particles were j examined to characterize the mechanical and chenical integrity of the irradiated fuel particles after irradiation. Observations for the kernel, buffer, IPyC, sic, OPyC and total coating are presented in Table 6. The irradiation performance of the fuel particles was judged to be very good after being exposed to a fast neutron fluence of approximately 1.9 x 1025 n/m2 (E 7 29 fJ)HIGR and a. time average temperature of approximately 7000C (Ref. 2). Representative photo-micrographs of typical particles are shown in Figs. 26 and 27 l l 7.2.2.1 Observations on Fuel 1(ernelm The irradiated (Th,U)C2 and ThC2 fuel kernels were very uniform and underwent minimal observable structural change with the exception r j of three (Th,U)C2 kernels. One (Th,U)C2 fuel kernel was observed to.- _..

i TITLE: DESTRUCTIVE EXAMINATION ~ 0F FURT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTEr2 ISSUE N/C have some cracking as a result of kernel swelling and buffer densifi-cation as shown in Fig. 28. 1Wo (Th,U)C2 kernels exhibited localized swollen areas which extruded into cracked regions of the buffer coat-ings as shown in Fig. 29. These phenmena were also observed in the Peach Bot;ta Test Element Program (Ref.13) and also in capsule F-30 ( Ref. 12). Fuel kernel migration is a potential fuel failure mechanisn. All particle coatings that come into contact with a migrating kernel are chenically degraded. Carbide fuels migrate by diffusion of carbon tarough the kernel with disposition of carbon behind the kernel ( Ref. 13). This type of kernel migration was not seen in the fissile and fertile particles. ] 7.2.2.2 Observat.,ns on the Buffer Continas l l 1he buffer coating of the fissile and fertile particles densified during irradiation. In most cases the buffer coatings shrank onto the kernels leaving a gap at the IPyC/ buffer coatir.g interface (Fig. 30). The fissile particles were fabricated with a 5/4m high-density seal i coating applied over the buffer coating. The seal coating allmed the buffer coating to decouple fra the IPyC coating during the buffer coating densification. The fertile particle buffer coating exhibited' a high incidence of cracking (Fig. 31). This was not unusual con-sidering the kernel swelling in ThC2 fuel kernels during irradiation. Even though a higher fraction of buffer coatings cracked in the fertile particles, this is consistent with observations fra F-30 ( Ref. 12). The buffer coatings in both particle types served their

TITLE: DESTRUCr1VE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEMENT FTFr2 ISSUE N/C functions of accommodatirg kernel swelling and protecting the struct-u al coatings fra fission product recoil damage and interaction with the fuel kernels. 7 2.2.3 Observations on the Inner Pyrolytic Carbon Contina Re IPyC coatings of botn the fissile and fertile particles per-famed very well. he mall fraction (approximately 1%) of observed IPyC coatings which failed or debonded fra the sic coating resulted fra irradiation induced densification. Figure 32 gives typical examples of these observed phenmena. he IPyC coatings remained intact and bonded to the sic coatings in 99% of the observed parti-cles, thus providing additional structural stability and strength to the composite coatings. Rese observations are consistent with the results of F-30 (proci test capsule) and the examination of FSV element S/N: 1-2415 (Refs.12 and 14). 7.2.2.4 Observations on the Silicon Coatina Re sic coating perfomance was judged to be very good as evi-denced by the low coating failure fractions. Be examined fissile particles exhibited sic coating failure of 0.7% and the fci tile particles had sic failure of 0.5%. None of the observed cases of sic coating failures resulted in failures of the remaining structural coating. Figure 33 shows the observed sic failures. Lenticular inclusions in the sic coatings were observed in 1.1% of the fissile particles and in 2.2% of the fertile particles. Figure 34 shows this type of flaw. Flaws of this type were seen in the

TITLE: DESTRUCTIVE EXAMINATION OF FORT DOC. No. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C examination of FSV elanent 1-2415 and in capsule F-30 (Refs.14 and i 12). Electron microprobe analysis of tmirradiated particles fran the F-30 capsule revealed that these inclusions consisted almost entirely l of carbon with trace amounts of thoriun, silicon and chlorine ( Ref. 12). The presence of the inclusions did not appear to adversely affect the mechanical integrity of the sic coatings nor can any of the sic coating failure be directly attributable to these inclusions. 7.2.2.5 nhmervation on tha Outer Pyrolytic Carbon Contina The perforinance of the high-density OPyC coatings in the fissile and fertile particles was excellent. There were no observed coating failures nor signs of chenical degradation by the matrix or fission pro & cts. Thus, there were no total particle coating failures. i 7.2.2.6 observatiana on the Charnical Degradation of Coatinas The chemical behavior of the TRISO particles was as expected. In i the fertile particle, there were no observed signs of fission product interaction with coatings nor chenical degradation of ary coatings. 1Wo fissile particles were observed to have fuel dispersed throughout the buffer and IPyC coatings (Fig. 35). In one of the particles, the IPyC had completely degraded in one spot and the chenical interaction had begun degrading the sic coating. The reaction penetrated about 4/4m into the sic layer. Penetration depths on the order of 10 to 15#m might lead to some volatile fission proect metal release, but the penetration depth was significantly less. Also, the degree of fuel dispersion and chenical interaction of fission products with coatings was less than observed in FSV elenent 1-2415 (Ref.14). l P i. - - - - - - - -. -.... - - - -

TITLE: DESTRUCTIVE EXAMINATION OF FURT D0C. No. 908909 ST. VRAIN FUEL TEST ELEMENT FTE-2 ISSUE N/C 7 3 Monitor Evaluation FTE-2 was equipped with 36 monitor crucibles as shown in Fig. 6. Six of these monitors were slated for evaluations of fluence and turn-up (Section 7.3.3). Visual examinations, evaluations, ard analyses of the monitors follcw. 7 3.1 Vi= =1 Er=ination of Monitor crucibles The monitors were very difficult to retrieve and in most cases had to be cut fra the elenent (see Section 6.3 4). Since monitor cruci-bles were not in the elenent during the cured-ird place process, and the initial fuel hole-monitor gap' (0.0045 inch) was sufficient, it l was concluded that the crucibles enlarged during irradiation. The visual appearance of the retrieved monitors supports this conclusion. All retrieved monitors were cracked. Monitors located on the top of the CIP stacks showed less cracking than the monitors located in lower axial positions. Figs. 36, 37, and 38 show typical top moni-tors. Cracking was more pronotriced in the second and third monitors of the 4 monitor stacks. Examples are shown in Figs. 39, 40 and 41. Sme of these crucibles fell apart when removed fran the supporting walls of the fuel hole. Force was applied to the fourth and first monitors during retrieval attenpts which could have added to their damage. Also, a few crucibles were cut slightly during the cutting out retrieval. There was no observed cracking of the fuel hole walls adjacent to where crucibles had been. eg,p = (Dianeter of Hole - Dianeter of crucible) 2 - _ _. - _ _ - __-

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C l 7.3.2 Diagn== ton or Monitor crucible observations 1he monitor crucible is a neer isotropic H-451 graphite rod machined with seven crucible holes and a threaded cap. The monitoring devices are located in the holes as shown in Fig. 5. Four holes con-tain dosimetry wires for fluence measurements. Each desimetry wire is i encased in an alumina tube with altaina plugs in aach end. The altains tubes are placed inside of a niobium-15 zircopita (Nb-15 Zr) tube with (Nb-15 Zr) welded ends. Four of the seven crucible holes have these niobita alloy tubes. A temperature monitor, which is a silicon carbide rod, is placed inside of the central crucible hole. l The last two holes are filled with burnup monitors which are contained in anall H-451 graphite holders with caps. Six of the 36 installed monitors were analyzed (Section 7 3 3). In all of the analyzed monitors, the H-451 graphite particle holders and silicon carbide rods slipped out of the crucibles easily and maintained their structural integrity with the exception of one silicon carbide rod which broke. The broken silicon carbide rod pieces slipped out of the crucible easily and showed no other signs of deterioration. Hw ever, most of the niobita tubes containing the dosimetry monitoring had deteriorated to the point of losing their integrity and some ertabled away. Nearly all of these tubes were extremely tight in the crucible. In most cases the crucible had to be crushed in order to remove the Nb-15 Zr tubes. The altaina tubes located inside of the friable Nb-15 Zr tubes maintained their structural integrity. Measurenent on one altaina tube stiawed no increase in length nor in diameter. . t ( - - - - - - -

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C Based on these observations, the suspected cause of the swelling and cracking of the crucibles were the Nb-15 Zr tubes. Berefore, a metallogra#11c mount was prepared to observe the microstructure of an in situ Nb-15 Zr tube and an mirradiated standard Nb-15 Zr tube. The mount was prepared by sectioning a crucible with two in-situ Nb-15 Zr tubes and one emptied hole. The mirradiated Nb-15 Zr tube was placed in the crucible hole. The alunina tubes and dosimetry wires were removed fran the Nb-15 Zr tubes. The mount was set in resin, ground, and polished. The polished surface was examined under bright field illunination with the Leitz metallograph. There was a marked difference in the microstructures between the irradiated Nb-15 Zr tubes and the mirradiated standard Nb-15 Zr tube. Figures 42 and 43 show the metallographic mount. The irradiated tubes i showed fractures, void formations and swelling. The irradiated tubes canpletely filled the crucible holes. There were cracks in the cruci-i ble fran the holes which contain the irradiated Nb-15 Zr tubes.

Also, measurenents of the diameters showed approximately a 14% diametral j

expansion relative to the unirradiated standard. The cause of the observed swelling of the Nb-15 Zr tubes has not been isolated. This niobiun alloy has been used successfully in other irradiation experiments (Ref. 10). There are several factors which could have caused the swelling. Irradiation-induced swelling of Nb-15 Zr tows a peak of ~2 volune 5 at an exposure of 5.4x1022 n/cm2 at 8000C and could not have caused the observed swelling. At elevated tanperatures (8000C - 10000C) and during slow cool down, impurities i o !

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELDENT FTFe2 ISSUE N/C l such as oxygen,

carbon, nitrogen and hydrogen can induce void formation / swelling by fonning canpoteds with the niobitan (Ref.11).

l There was opporttmity during water ingresses into the core for such impurities to enter into the systen. 7 3.3 Monitor Analvaia and Raan1ts Six monitor packages were transported to Qianistry for analyses of the fluence and burnup monitoring devices. They were the first monitor of holes 18, 67 and 30T; the third monitor of hole 86; and the fourth monitor of holes 131 and 239. Inspection of each package upon runwal fran the cask generally revealed severe cracks in the outer graphite container. In one or Wo cases large pieces of the container i had broken away. Nearly all of niobitan capsules were extranely tight in the graphite container. In most cases the graphite container had to be crushed to ranwe these capsules and obtain the wires inside i then. The silicon carbide rods, used to measure tanperature, were ranwed and saved. The No H-451 graphite tubes containing the burnup i samples were remmed and identified. Selected UC2 fissile and ThC2 fertile particles underwent burnup analyses. The coated particle attributes are presented in Table 7. The particles were analyzed using a radiochenistry method anploying Cs-137 as a burnup monitor. The details of the analysis are provided in Appendix B. The results are stenarized in Table 9. The average measured fissile FIMA (fissions per initial heavy metal atan) was 475 i 6% as compared to a calculated value of 455. The average measured fertile FIMA was 1.1% A 0.1% and the calculated fertile FIMA was 0.95. The calculated FIMAs are elenent average values. Local variations within the elenent can be as large as i 10 to 15%. t

TITLE: DESTRUCTIVE EXAMINATION OF FORT DOC. NO. 908909 ST. VRAIN FUEL TEST ELDENT FTS-2 ISSUE N/C Four types of dosimeters were included in the monitor packages. The vanadiun and vanaditm>-cobalt wires were for measuring the thennal neutron fluence. The vanadita-iron and magnesiun oxide-nickel oxide wires were for measuring the fast fluence. The reactions of interest for the dosimeters are listed in Table 8. The magnesiun oxide-nickel oxide wires were not included in the data since no nickel cross sections were available. The dosimetry wires were subnitted for gama ray spectral analysis. The measured activities for the radionuclides of interest were back-<iecayed to end of life and used to compute the fast and thennal fluences. The detailed analysis is provided in 25 Appendix B. The averaged measured fast fluence was 1.6 x 10 n/d j as compared to a calclated value or 19 x 1025 n/ni2 The average measured thermal fluence was 3.8 x 1025 n/ni2 where the calculated thennal fluence was 3.3 x 1025 n/m2 The results of the analysis are summarized in Table 9 7.4 Granhite Annivnin and Evaluation As a part of the destructive postirradiation test progran of FTE-2, coupon specimens were cored fran the graphite block and used for measuring the mechanical and thermal properties of the irradiated graphite. The measured properties were canpared with the design l values given in the Graphite Design Data Manual (Ref.15) in order to i validate the design assumptions for H-451 graphite fuel elenents. l This section describes the measurenents of tensile strength, Young's modulus, tensile fracture strain, and thennal expansivity. 1 Thermal diffusivity measurenents were also planned as a part of the i i l ,_~.,---,.m., _ _. _ ___

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTEr2 ISSUE N/C test progra, but due to the late delivery of a replacement laser for the themal diffusivity apparatus, the test data will be reported later in Ref.16. 7.4.1 Materig Test elment FTE-2 was made frm Great Lakes Carbon Corporation grade H-451 graphite, development lot 426. The elment was renoved fra core location 22.06.F.06 after accmulating 483 equivalent full power days. The approximate neutron fluence nyt was 1.9 x 1025 n/m2 (E > 29 fJ) and the approximate calculated operating temperature was 5100C. The elenent was cut up in the GA hot cell and cores were taken fra a 7 inch deep slab located as shown in Fig. 20. Cores were taken fran four of the six faces of the slab (faces A, B, E and F). An extra set of transverse cores was taken fra face B. Figures 44, 45, 46, and 47 show the location of the cored samples. l The cores were transferred fran the Hot Cell to the Graphite Laboratory and machined to size in a lathe set up in a hood with an absolute filter in the exhaust systen. A second high suction exhaust systen with a separate absolute filter was used to trap machining dust. The final machined dimensions of the test specimens are shown in Table 10. Several of the specimens cracked during machining and were replaced by specimens fran extra cores. The test specimens were identified by the core nunber as shown in Figs. 44-47, followed by the e __. _

TITLE: DESTRUCTIVE EXAMINATION OF FORT DOC No. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C letter A or B, with the A specimen being closest to the cut edge of the slab. Be nunber of replicate thermal expansitivity measurenents was reduced fran 3 to 2 because the reproducibility was very good and the third test was not necessary. 7 4.2 Test Methods 7.4.2.1 Tensile Properties he test specimens were cemented between aluninun end pieces with high strength epoxy actiesive, using split shell alignment fixtures to maintain the specimens coaxial with the end pieces. Bey were then mounted in an Instron model 1122 testing machine, using chain linkages to apply the load. De crosshead speed was set at 0.005 in./ minute. No 0.5 in. gauge length extensometers were clipped onto opposite sides of the specimen. A plexiglass enclosure exhausted through an absolute filter surrounded the the test assembly. Be stress on the specimen was raised to 1000 psi, reduced to 100 psi, and then increased until the specimen fractured. Le extensometer and load cell signals were processed by a MINC II laboratory computer which stored the data and calculated the ultimate tensile strength, fracture j strain, and Young's modulus. Young's modulus was calculated fran the least squares regression line through the stress-strain data points over the 100 psi to 1000 psi reloading part of the curve. Strain values used in the calculations were the mean of the two extensometer readings. Further details of the test method are given in Ref.17.

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELENENT FTF-2 ISSUE N/C 7 4.2.2 1herwal Ernansivity The thennal expansivity measurenents were made in a fused silica dilataneter in an atmosphere of hellun. The dilataneter enclosure was ~ exhausted through an absolute filter. The temperature was raised fran roan temperature to 6000C at 3cC/ minutes. The thennal expansivity was calculated fran the dilatation at 5000C. Initial calibration of the instrunent was made using a built-in micraneter to move the sensor over a span of 0.005 inch. For a firm 1 calibration, a National Bureau of Standards tungsten reference specimen (!ES standard reference material 737) was measured before and after the series of tests. The expansion of the standard specimen as measured by the dilataneter was 65 1cwer than the NBS certified value at 5000C. The gra;ttite expan.- sions were therefore corrected by a factor of 1.06 to bring the measurements into confonnity with the NBS standard reference material. Further details of the test method are given in Ref.18. 7.4 3 Results 7.4.3.1 Tensile Pronerties The test results for the tensile strength, Young's modulus, and fracture strain of the axial specimens are shown in Table 11, and those for the transverse specimens are shown in Table 12. Due to a canputer error the strain data for the first four axial specimens fran face A were lost. The data are sumnarized in Table 13 and plotted for eacit face of the block in Figs. 48-50. The Design Data Manual (DDH) values (mean and standard deviation) for the tensile strength and Young's modulus are shown in Table 13 and Figs. 48 and 49. These

TITLE: DESTRUCTIVE EXAMINATION OF FDRT D0C. NO. 908909 ST. VRAIN RIEL TEST ELEENT FTF-2 ISSUE N/C H D values were taken fran Ref.15, section 2 3.5. Unirradiated property values were taken to be the mean of the listed values for the end-edge and midlength-edge locations in the billet. To allow for the effects of irradiation to 19 x 1025 n/m2 at 5100C, the unirradiated tensile strengths were multiplied by a factor of 1.56 and the unirradiated Yotmg's moduli were multiplied by a factor of 2.00 (Ref.15, Table 2.3-5 and equation 2.3-5). The tensile properties show no clear systematic trend with the face of the fuel elenent (Figs. 48-50). The two sets of transverse specimens fran face B (Fig. 45) had similar properties. The tensile strengths are in good agreement with the Design Data Manual values (Fig. 48). The Young's moduli fall at the low end of the band pre-dicted by the Design Data Manual (Fig. 49), but there is no signifi-cant inconsistency. 7.4.3.2 hr==1 Ernansivity The thermal expansivity measurenents (25-50000) are listed in Table 14, and plotted for each face of the block in Fig. 51. The Design Data Manual values (mean and standard deviation) are included in Table 12 and Fig 51. These values were obtained by averaging the values for end-edge and midlength-edge locations (Table 2.3-10, Ref.

15) and multiplying by a factor of 1.145 to allow for the effects of irradiation (Eq. 2.3-16, Ref.15).

There is no systanatic face-to-face trend in the measurements, and the two sets of transverse specimens from face B are in agreenent (Fig. 51). However, unlike the tensile properties, the measured t l l. __ _.

TITLE: DESTRUCTIVE EXAM 5ATION OF FORT DOC. No. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C thennal expansivities fall belm the Design Data Manual values for both the axial and transverse directions. There are two possible explanations for the inconsistency. (1) The calculated operating temperature and neutron fluence for the test elment may be in error. The 1mer than expected thennal expansivities (and also the slightly 1mer than expected Young's moduli, Fig. 49) suggest that the block taperature may have been higher than the neinal value of 5100C for a substantial period. 2) The design polynmial for the change in thermal expansivity with irradiation may be in error. The data used to fit the polynm ial were obtained at 6000C and

above, and extrapolation to the lwer temperature of 510cc may over-estimate the irradiation-induced change.

Experimental verification of the fuel test element operating temperature (e.g., by analysis of the silicon carbide temperature monitors) is underwg and will be reported later in Reference 16. This evaluation will be useful to establish which explanation for the l inconsistency is more likely. i I . l E

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUE TEST El.EENT FTF-2 ISSUE N/C 8.0 ACKNOWLEDGEEN7S The author wishes to acknowledge the following contributors to ~ this report. Burnup and Fluence Monitor Analysis: Dale Hill (Chanistry) Graphite Core Sanple Analysis: Robert Price (Graphite Laboratory) Hot Cell Personnel: Walt Simpson, Jose Gcmez, John Greenwood and Harry Jdinson.

TITLE: DETRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN RIEL TET ELDelT FTS2 ISSUE N/C 9.0 REFERDiCES 1. Saurwein, J. J., " Nondestructive Examination of 54 Fuel and Reflector Elanents fran Fort St. Vrain Core Segnent 2," GA Technologies Report GA-A16829, October 1982. 2.

McCord, F.,

" Nondestructive Examination of 62 Fuel and Reflector Elanents fran. Fort St. Vrain Core Segnent 3," Document No. 907785, January 24, 1985. 3. Miller, C. M., "Preirradiation Characterization of FSV Fuel Test Elanents FTE-1 Through Fr&8," Docunent No. 904451, May 1, 1980. 4. Crockett, F. B. and McNair, J., " Design and Construction of Monitor Packages for Fort St. Vrain Fuel Test Elanents," GA Tedinologies Report GA-D146CTT,' Decenber 1977. 5.

Marsh, N.

I., " Safety Analysis Report for Fort St. Vrain Reload 1 Test Elanents FTG1 1hrough FT&8," Docunent No. GLP-5494, June 30,1977. 6. Malakhof, V. and W. Lefler, " Fuel Accountability at End of cycle 3 (294.5 EFPD)," Docunent No. 907402, Issue A, May 15, 1984. l l 7. Saurvein, J. J., " Test Report: Nondestructive Examination of FSV Fuel Test Elanent FTb1," Docunent No. 906599, Septanber 20, 1982. ( r-me +.- - - -- - - - - -_,, _,m, ..,_,,_,_y.- ,,___-.,__,.7,

TITLE: DESTRUCTIVE EXAMINATION OF FORT 00C. NO. 908909 ST. VRAIN FUEL TEST EEENT FT&2 ISSUE N/C 8.

McCord, F.,

" Test Procedure for Destructive Examimtion of FSV FTS2, S/N: 8-0206," Document No. 906771, Issue B, January 27, 1986. 9.

Saurwein, J.

J., C. M. Miller, and C. A. Young, " Post-irradiation and Evaluation of Fort St. Vrain Fuel Elm ent 1-0T43," GA Technologies Report GA-A16258, May 1981.

10. Ketterer, J.

and B. F.

Myers,

" Capsules HRB-16 Post-irradiation Examination Report," HIGR-85-053, September 27, 1985. (GA Document No. 908012).

11. " Conceptual Design Studies in Support of SP-100 Program,"

GA-C17354, Vol.1, December 9,1983.

12. Scott, C. B., and D. P. Hamon, "Postirradiation Examination of Capsule F-30," GA Technologies Report GA-A13208, April 1, 1975.

13. Saurvein, J. J., et al, " Final Report on the Peach Bottan Test Elanent Program," GA Technologies Report No. GA-A15999, l

Nov eber 1982. i l

14. McCord, F.,

"Postirradiation Examination and Evaluation of F3V Fuel Elment 1-2415," Docunent No. 907U79, September 30, 1983. 15. R. J. Price, " Graphite Design Data Manual," GA Docunent No. 906374, Issue A (9/27/84).

TITLE: DESTRUCTIVE EXAMINATION OF FORT D0C. NO. 908909 ST. VRAIN FUEL TEST ELEENT FTE-2 ISSUE N/C

16. Price, R.

J. and F. McCord, "Thennal Diffusivity of H-451 Graphite and Tenperature Monitor Analyses of FSV Fuel Elenent FTFr2," Docunent No. 908928, (to be published August 1986).

17. " Test Method:

Tensile Properties of Graphite," GA Docunent No. 904252, Issue A (9/12/79).

18. " Standard Method of Test for Linear Thennal Expansion of Rigid Solids with a Vitreous Silica D11ataneter," ASTM Test Method E-228.

l 1. ~-.. -. _ _

908909 N/C Table 1 Test Data and Objectives Data Methods Objectives A. Graphite Fuel Block 1. Structural integrity Visual examination Validate structural performance (also using data of H-451 graphite block. from Ref. 1) 2. Thermal expansivity Fused silica dilato-Validate axial and transverse meter CTE and identify any differ-ences between measured and predicted values. 3 Thermal diffusivity Heat-pulse Validate thermal diffusivity and identify any difference between measured and pre-dicted values. 4. Tensile strength Extensometer , Validate axial and transverse ltensilestrengthandYoung's ! modulus. B. Fuel Rods 1. Structural integrity Visual examination Check for acceptable structural (via Kollmorgan performance, look for signs of Periscope) fuel rod-graphite interaction. 2. Fuel stack push Force measuring ! Measure the extent of fuel out force (10 stacks device i rod-graphite interaction only) l 3 Microstructure Metallography Validate fuel performance C. Monitor Packages Provide reference points for 1. Fast and thermal Dosimetry measured and observed properties. neutron fluence Provide reference points for 2. Fuel burnup Radiochemistry measured and observed properties. 39 L

908909 N/C Table 2 Dimension Specifications 4 CA ORNI. and CEA 's I, hole diameter, mm (in.) 12.65[ 0.498[ i 0 0.001b} 0.25 t 12.70 + 0.10 k0.500+0.003) Coolant hole diameter, n m (In.) 15.88[0 0.625[0 0 0 (: een rod diameter, mm (in.) 12.421[0. 0.4890 + 005 " 12.45 1 0.013 (0.4900 1 0.0005)(" 5 Fired rod diameter,( mm (in.) 12.50 1 0.13 (0.492 1 0.005)(") 12.62 max (0.497 max)(b) 12.37 min (0.487 min)(b) Creen rod length, mm (in.) 49.28 (1.94)(d) Fired rod length, mm (in.) 49.28 1 0.76 (1.94 1 0.03)(b) Radial gap,I") (derived from specification), mm'(in.) Green 0.13 max (0.00525 max){(,) h.12 max (0.00475 max){g,) 0.06 min (0.00225 min) J 0.04 (0.00175 min) J Fired 0.15 max (0.006 max) { 0.04 min (0.0015 min) J(,) 0.18 max (0.007 max){(b) _.0 min _0 min J " FTE-1 through -6. FTE-7 and -8.

1. Process information only.

(d) Length tolerance is estahlished from assembly requirements and manufacturing data.

f 908909 N/C Table 3 Fuel Accountability of FTE-2 at the End of Cycle 3 SER'lAL NUNSER 8-0206 ACUQUNTASILITY Divre gf3gfg3

• 0RE LOCATION REGION 22 COLUMN 6

~ nam LAYER 6 SET 1 0F 7 (00E OWNE01 TICGCfET{ ~ HEAVY METAL WEIGHTS (GM) PARTICLE NUCLIOE INITIAL CURPENT FERTILE TH232 9058.59 8836.34 FERTILE PA231 .00 .04 FERYILE U232 .00 .03 FERTILE U233* .00 158.43 FERTILE U234 .00 12.30 FERTILE U235 .00 1 25 FERTILE U236 .00 .06 FISSILE TH232 5 03 4.89 FISSILE PA231 .00 00 ~-~ FISSICE U2 32 .00 .CQ FISSILE U233* .00 09 Fl55}LE U234 3.34 2. 3'9 FISSILE U235 425.56 171.78 FISSILE U236 1 28 46.52 FISSILE U238 26.68 23.92 FISSILE NP237 .00 2.89 FISSILE PU238 .00 .50 FI'S S ICE PU2B *= .00 .65 ~~ FISSILE PU240 .00 .25 FIYTICE PU241 .00 .24 FISSILE PU242 .00 .10 TOTAL 9550.46 9262.63 TOTAL FISSILE URANIUM 425.56 331.55 T6TAL URARIUM 456 85 416.78 1 ~~ TOTAC FISSICE PCfJTONIUM .00 .89 TOTAL PLUTONIUM .00 1.74 EFFECTIVE U233 ENRICHMENT, .00 38.03 ~ EFFECTI'VE72'is ENR ICHME NT, t 93 15 41.52 PPM U232 .00 67.66 FERTILE PARTICLE FIMA, t .00 .89 - -~ ~ ~ FISSILE PARTICCE FIMA It .00 45.03 BURNUP (MWQ/ TONNE) 28571.82 CUMULATIVZ f?FO 488 80 ~lNCLUDES FULL CECAY.0F PA233

• • INCLUDES FULL OECAY OF NP239
• x*

UC TRISO Fissile, Th0 TRISO Fertile 2 2 41

908909 N/C Table 3 (Continued) 51sTAL NUMSER F02 C6 ACCOUNTABI[l~TY DATE: 9/30/63 20RE LOCATION 1 REGION 2 ~ ~ " " COLUMN 6 LAYER' 6 517~~2 0F 7 (PSC OWNE01 'Ill M34 ~< HEAVY METAL WEIGHTS (GM3 PARTICLE NUCLICE INITIAL CURRENT ' ' ~ ~ FERTILE TH232 155 47 150.89 FERTILE PA231 .00 .C0 F[RTI[l U 2'IZ .00 .00 FERTILE U233* .00 2.84 FER TICE U234 . 0'O . 23 FERTILE U235 .00 .C2 FERTILE U236 .30 00 fl55ILE TH232 59.34 57 59 FISSILE PA231 .00 00 ~ ~ ~ FI S'5 ICE U2 32 .00 .00 FISSILE U233* .00 1 08 FISSILE U234 .12 .17 FISSILE U235 11.88 4.80 F155ILE U236 .04 1.30 FISSILE U238 48.38 45.35 FI'55 ICE NP237 .00 08 ~ FISSILE PU238 .30 01 FI55 ICE-- P'U'239*= .00 .67 FISSILE PU240 .00 .27 FYYTICE Pu241 .00 .26 FISSILE PU242 .00 .10 TOTAL 275.22 265.68 TOTAL FISSILE URANIUM 11.88 9.75 T O'T A CTR'ATIU M 60.41 55.81 TOTAC FIS$'ILE PCUTONI6M .00 .93 ~ TOTAL PLUTCNIUM .00 1.31 EFFECTIVE U233 ENRICHMENT, 3 .00 7.04 EFFECTI9E~IiY35 EPTR'ICHTE N f, % 19 66 8 64 ~ PPM U232 .00 11.94 FERTILE PARTICLE FINA, 3 .00 .96 ~~~F I S S IL E P A R T ICLE ~ F IM AI-~% .00 6 72 ~ ~ BURNUP (MWO/ TONNE) 32904.92 C(IM0EA~Tl W CF#0 488 80 l INCCUC E S F ULTO ECA'Y 0 F plt 33 -~

• • INCLUDES FULL OECAY OF NP239
    • (Th,U)0 TRISO Fissile, Th0 TRISO Fertile 2

2 42 i

908909 N/C Table 3 (Continued) ~ Stil'AL NUMBlh 8-0206 ACCOUNTABILITY DATE: 9/30/s3 e CORE LOCATION REGION 22 COLUMN 6 ~ ^^^ LAYER 6 SET 3 0F 7 (PSC OWNEDI I:f7'(3L ]' HEAVY FETAL WEIGHTS (GM1 PARTICLE NUCLICE INITIAL CURPENT FERTILE TH232 237.36 230.75 FERTILE PA231 .00 .00 FESTILE U232 .00 .00 FERTILE U233* .00 4.11__ FERTILE U234 .00 .32 FERTTLE U235 .00 03 FERTILE U236 .00 .C0 FISSILE TH232 64.65 62.35 FISSILE PA231 .00 00 FISSILE U2 32 .30 .C0 FISSILE U233* .30 1.13 FISSILE U234 .11 .1T FISSILE U235 14.26 5.76 FISSILE U236 .04 1.56 FISSILE U238 .89 .80 FISSILE NP237 .00 .10 FISSILE PU238 .00 .02 FISSILE PU239*= .00 .02 FISSILE PU240 .00 .01 FISSILE PU241 .00 01 FISSILE PU242 .00 .C0 TOTAL 317.33 307.69 TOTAL FISSILE URANIUM 14.26 11.C8 TETAL URANIUM 15.31 13.93 ~ ~~ TOTAL FISSILE PLUTONIUM .00 .03 TOTAL PLUTONIUM .00 .06 EFFECTIVE U233 ENRICHMENT, t .00 37.92 EFFECTITC U235 lVRICHMENT, t 93.15 41 58 ~ PPM U232 .00 67.20 FERTILE PARTICLE FIMA, t .00 90 , _,, _,_, FISSILE ^ PARTICLE FIMA, .00 9.35 8URNUP (MWO/ TONNE) 28813.29 CIIM'UTl'TTYE~ETP'O 4S8 80 ~ ~ ~ ~ ~ - '

• INCLUDES FULL DECAY O'F P A'l33
  • INCLUDES FULL DECAY OF NP239
    • (Th,U)C TRISO Fissile, ThC TRISO Fertile 2

2 43 ~

908909 N/C Table 3 (Continued) SCRlAL NUMefR S-0206 ACCQUNTABILITY DATE: 9/3C/83 _00_R_E LOCATION " ~ ~ ' ~ COLUMN 6 r LAYER 6 SET 4 0F 7 (CEA OWNE01 l ~C. E AME - ~ ~ " ~ ~ ~ HEAVY METAL WEIGHTS (GM3 - ~ ~ ~ ~ ~ '~P AR TICEE NUCLICE INITIAL CURRENT FERTILE TH232 3G7 12 298.5& ~ FERTILE PA231 .C0 .00 Fi~R T ILE U232 .00 .00 ._. _ _ _ _FERT..ILE. U233* .00 5.I6 pq- ~ ~ ~ ~ FERTILE U235 .00 04 FERTIEt U236 .00 .C0 FISSILE TH232 .00 .C0 FISSILE PA231 .C0 .C0 FISSILE U232 .00 .00 FISSILE U233* .00 00 FISSILE U234 .11 08 FISSILE U235 la.07 5.67 FI' STILE u236 .Q* 1 54 FISSILE U238 .88 .79 FISSILE NP237 .00 .10 FISSILE PU238 .00 .C2 ~ ~ ~ ~ ~ FI S'S I L"t P O 2'3 9 m m .00 02 FISSILE PU240 .00 01 F'ISSILE PU241 .00 01 FISSILE PU242 .00 00 TOTAL 322.23 312.64 TOTAL FISSILE URANIUM 14.07 11.08 T O Ti'L'~ U R' A N IU M 15.11 13 91 ~ ~~~ ~~ ~~' 'T O T A L F I S S IL E P LU T ON IUM .00 .03 TOTAL PLUTONIUM .00 .06 EFFECTIVE U2 33 ENPICHMENT, t .00 38.55 ~ ~ ~ ~ EFFECTIVE U235 ENRICHMENT, = 93.15 41.10 PPM U232 .00 68.46 FERTILE PARTICLE

IMA,

_ _,, _, FISSILE, PARTICLE [FIMA,_: .00 _.89 .CC 45 54 EURNUP (MWD / TONNE) 28215 29 CUMULATIVE ~EPPO ESS.8C INCLUDES FDLl~~0ECAY OF PA233

• = INCLUDES FULL CECAY OF NP239_,

e _ a 44

908909 N/C Table 3 (Continued) - '2'0 6 A ChifuTA E~ILITY 0 ATE: 9/30/33 G t SERIAL.NUMBE9 8 CORE LOCATION '~~~~~ REGION--22 COLUMN----6 , f-apy-}. ~ HEAVY METAL WEIGHTS (GM) ~ ~ ~ ~ ~ ~ - ~ ~P AR TICLE N tic L ID E INITIAL CURRENT ~ FERTILE TH232

1. 59.95 447 1a FERTILE PA231

.00 .00 FERTICE U232 .CC .00 "~--" -~~ ~ FERTILE U233* .00- .62 S.02 FERTICE U224~ .00 FERTILE U235 .00 .C6 FERTILE U236 .00 .00 FISSILE TH232 .00 .00 FISSILE PA231 .00 00 ~~ FISSICE U232 .00 .00 FISSILE U233* .C0 00 FISSILE U2Y4 .18 .13 ~ FISSILE U235 22.91 9.27 FYY37L'E U236 .07 2.50 FISSILE U278 1.44 1.29 FI S'S I CE NP23'7 .00 .16 FISSILE P U_2 3_8 .00 .03 FISSICE PU230** .00 .c4 FISSILE PU240 .00 31 FITTICE Pul41 . 0'O 01 FISSILE PU242 .00 01 TOTAL 424.55 469.33 TOTAL FISSILE URANIUM 22.91 17.35 TOTAL URANIUM Zu.59 21.90 TOTAL FISSILE ~ PLUTONIUM .00 .05 ~ TOYAL PLUTCNIUM .00 .09 l EFFECTIVE U233 ENRICHMENT, t .00 36.63 EFFEC T I9 E~U2~35 EVN ICH'REET, 9'3.15 42.61 PPM U232 .00 65.13 FERTILE PARTICLE FIMA, t .00 +89 - ~' ~~ ~ ~ ~ -- - ~ F I S S ILE 'P A R T ICL'E F IM A,"~t ~ 700 45 44 o BURNUP (MWO/ TONNE) 29763.C2 CtIMOCrTITC ETPO saa.80 - ~ ~ ~ ~ INCLUDES FUCL DECAY-~ ~ I23i ~ - - 0F P ~ ~

• • INCLUDES FULL DECAY OF NP239 _,, _ _ _ _ _ _.

45

908909 N/C Table 3 (Continued) k -~ sERI~AC NOMSER 8702C6 . LCCO U N T A B ILIT ~Y DATE: 9730/83 ~ ~ ~ ' CORE LOCATION REGIONif~ COLUMN 6 LAYER 6 SET 6 0F T (00E QWNED) CMC HEAVY METAL WEIGHTS (GM) P AR TICEt AUCETOE INITIAL CURRENT FERTILE TH232 307.03 295.50 FERTILE PA231 .00 .00 Y ~- FE TICE U232 .00 .CC FERTILE U233* .00 !.36 ~ ~ - - FERTILt U234 .00 42 ~ FERTILE U235 .00 .C4 FERTICE U236 . 0'O 00 FI5SILE fH232 .00 .C0 FISSILE PA231 .00 .C0 FI55' ICE U2 32 .00 .00 FISSILE U233* .00 00 F'I $37 CE U234 .12 08 FISSILE U235 14.79 5.97 FIY37t! u236 .04 1.62 FISSILE U238 .93. .83 FISSILE sp2T7 .00 .10 FISSILE PU238 .00 .02 FI S S I CE --) U'2Y9 * * . 0 0' . 0 2' FISSILE PU240 .00 .01 FI'53*I CE Pul41 . 0'O .01 FISSILE PU242 .00 .00 TOTAL 322.91 312 99 TOTAL FISSILE URANIUM tu.79 11.37 TfTAE U~RIhlUM 15.88 14.32 TOTAL FISSILE PLUTONIUM .00 .03 ~' TOTAL PLUTONIUM .00 .06 EFFECTIVE U233 ENRICHMENT, t .00 37.40 EEFECTIfE TZ35 ENRICliREET, s 91 15 42701 PPM U232 .00 66.50 FERTILE PARTICLE FIMA, t .00 .89 ~ ~ ~ " i ~~ ~ ~~~ FISSILE ~ PARTICLE ~FIM1 72- .00' 4574'9 BURNUP (Mh0/ TONNE) 29125.88 CtTM uTA7 IV'E"TFD'O

1. 88 80 J

-~~ e INCLUDES FUCC DECAY OF ~P4 233 .,,I.yC LU D E 5_ _ F,U_L_L D EC A Y OF NP239 1 46

908909 N/C Table 3 (Continued) 5E'R'IAL NUM81R 8-d2C6 A CCOUNT AB ILITY DATE: 9/30/83 ~ 20RE LOCATION REGION 22 COLUMN 6 fcR.NL1Vj~~~~' LAYER 6 SET 7 0F T (00E OWNED) ~ HEAVY PETAL WEIGHTS (GM1 P AR TICL'E NUCLIOE INITIAL CURPENT ~ ~ ~ 'fETT LE TH232 147.63 ~ 143.53 - - ~ ' ~ ~ ~ ~ FERTILE PA231 .00 .00 FERYICE U232 .0G .C0 FERTILE U Z_3 3 * .00 2 57 FERTILE U234 .00 .20 FERTILE U235 .00 02 FERTILE U236 .00 .C0 FISSILE TH232 .00 .00 FISSILE PA231 .00 00 TI$5ICT U2 32 .00 .00 ~ ~ FISSILE U233* .00 00 F.'Y3 ICE U234 . 0 5' 04 FI55ILE 'U235 6 94 2.30 FYlllLE U236 .02 .76 FISSILE U238 43 .39 Fi s5' ICE NPY3'T .00 05 FISSILE Pu238 .00 01 FI S 5IL'E PU'239s* .CO 01 ~ ~ ~ " - ~ ~ FISSILE PU240 .00 00 FliTIL'E PU241 .00 00 FISSILE PU242 .C0 .C0 TOTAL 155 07 150.39 TOTAL FISSILE URANIUM 6 94 5 39 T O T A L U R~AWIu'M 7.45 6 78 ~ ~ ~ ~ TOTAC~FI55 ICE ~PLUToriIUM .00 .01 - ~'~~~ ~ ~ TCTAL PLUTOMIUM .00 .03 EFFECTIVE U233 ENRICHMENT, t .00 37.44 l EFFECTIVE U22$~1NhTDEEENT, t 93.15 41 59 ~ l PPM U232 .00 67.50 t FERTILC PARTICLE FIMA, t .00 .89 ~ ' ' ' ~~ ~ ~F I S S IL E ~P A R T I CCE ~F IM A,~ t ~~ ~ ~~0 0~ ~~ '- ~4 5 75 2 '~ SURNUP (MWO/ TONNE) 28646 85 COMUCYTIVE EFPO

1. 88 80 l

~~ t

• I N C L U D E S-F U CC-'O E C A' YOF~PA233
  • INCLUDES FULL DECAY OF NP239 i

~ h 47 . -. ~. -.. - - -

908909 N/C TABLE 4 PUSBOUT FORCES Maximum Force at Removal Attempts (lbs) Method Hole Fuel Cured Spacer of Substaining of No. Array By First Max. Force Second Third Force Monitor (s) Removal i 2 Driver CIP 500 6 400 50f5 Push Device 4 Driver CIP 100 5 NM Push Device 5 Driver CIP 120 5 50 Push Device 7 Driver CIP 110 NM 5 Push Device 8 Driver CIP 350 2 NM Push Device 10 Driver CIP 150 6 NM Push Devico 12 Driver CIP 100 5 NM Push Device -14 Driver CIP 140 7 NM Push Device 15 Driver CIP 110 6 NM Push Device 17 Driver CIP

150 6

NM Push Device 1 18 Driver CIP '160 7 NM 1 Push Device 20 Driver CIP .350 7 NM Push Device 21 Driver CIP 160 6 NM Push Device 23 Driver CIP 190 7 NM Push Device 25D** Driver CIP 500 700 Cut, Pushed 26D I Driver CIP 500 700 Cut, Pushed I i 28 Driver CIP 140 7 NM Push Device 29 Driver CIP .500 7 500 50/5 Push Device 31 Driver CIP 500 7 600 250/5 Push Device j 32 Driver CIP 500 6 400 50/5 P tsh Device 34D Driver CIP 500 650 700 Cut, Pushed I 35D Driver CIP 500 650 700 Cut, Pushed 37 Driver CIP 300 6 NM Push Device 38D Driver CIP 500 650 700 Cut, Pushed 40D Driver CIP 500 650 700 Cut, Pushed I 41 Driver CIP 490 5 700 700 Cut, Pushed l 43 1 CIB NM NM Manual 44 1 CIB 16 10 Manual 46 Driver CIP 500 5 700 Cut, Pushed 47D Driver CIP 500 650 700 Cut, Pushed 49D Driver CIP ,500 650 700 l Cut, Pushed NM = Not Measured D = Stack located under a dowel l Min., NM = Minimal' effort, not measured

908909 N/C Table 4 (continued) Maximum Force at Removal Attempts (1bs) Method Hole Fuel Cured Spacer of Substaining of No. Array By First Max. Force Second Third Force Monitor (s) Removal 50 Driver CIP 500 7 700 5 Push Device. 51 Driver CIP 500 7 Cut, Pushed 53D Driver CIP 500 700 700 Cut, Pushed 54D Driver CIP 500 700 700 Cut, Pushed 56 Driver CIP 490 6 400 5 Push Device 1 57 1 CIB NM NM Manual 59 1 CIB 500 4 Cut Out 60 Driver CIP 500 5 650 Cut, Pushed l 62D Driver CIP 700 Cut, Pushed j 63D Driver CIP 700 Cut, Pushed l 65 Driver CIP 500 NM 600 100/5 Push Device 67 Driver CIP 175 NM 60/5 1 Push Device { 68 Driver CIP 500 6 700 Cut, Pushed j 70 Driver CIP 500 7 700 50/5 Push Device j 71 Driver CIP 500 5 650 Cut, Pushed i 73 1 CIB NM NM Manual j$ 74 1 CIB NM ? NM Manual 76 Driver CIP 500 6 700 Cut, Pushed 77 Driver CIP 500 4 700 Cut, Pushed ] 79 Driver CIP 500 6 700 Cut, Pushed 80 Driver CIP 500 6 700 700 Cut, Pushed 82 Driver CIP 400 NM 15 Push Device l 83 Driver CIP 500 NM 700 Cut, Pushed 85 6 CIP 50 NM 5 Push Device 86 6 CIT 500 700 4 Cut Out 88 Driver CIP 500 4 700 Cut, Pushed l 89 Driver CIP 500

4 700 Cut, Pushed 91 Driver CIP 490

6 700 i

Cut, Pushed 92 i Driver CIP 500 6 450 NM Push Device 94 2 CIT Min.,NM***- NM Manual 95 l 2 CIT Min., NM i Manual 97 Driver CIP 500 5 450 NM 1 Push Device 98 Driver CIP 500 7 450 NM Push Device 99 Driver CIP 200 j 20 Push Device l i

] 908909 N/C Table 4 (continued) i MaximumForceatRemovalAttempts(1bsh Method of Hole Fuel Cured Spacer of l Substaining I No. Array Ey First Max. Force ! Second Third Force Monitor (s) Removal i I 101 Driver I CIP 500 NM 400 5 Push Device f CIP 80 4 i NM Push Device 102 6 l CIP 80 4 NM Push Device 104 6 105 Driver CIP 500 6 700 700 Cut, Pushed + 1 107 Driver CIP ,470 4 700 700 Cut, Pushed i 108 Driver CIP

490

6 275 NH 1

Push Device 1 110 Driver I CIP i475 5 650 700 Cush, Pushed 111 2 CIT I Min. NM j-NM Manual 113 2 CIT 3 Min.NM l-I NM i Manual 114 j Driver ! CIP i500 j3 650 { l Cut, Pushed 116 i Driver CIP i500 !6 500 I NM l Push Device 118 i Driver j CIP !490 j6 50/2 Push Device 119 i Driver. CIP 490 i4 i 700 1 700 Cut, Pushed l f NM f CIP I

70 j3 Push Device 121 6

122 6 i CIP 75

NM j NM Push Device d

124 Driver CIP 480 5 i 700 l 650 i Cut, Pushed t i 125 Driver CIP 500 6 i 700 ? 700 Cut, Pushed ) $ 127 Driver CIP 140 7 I NM Push Device i 128 Driver CIP 500 6 480 l ! NM Push Device 130 2 CIT Min. NM NM Manual 4 Cut Out 131 2 CIT 500 700 i 133 Driver CIP 475 5 650 NM Push Device 134 Driver CIP 475 5 650 l 450 Push Device 136 Driver CIP ! 160 4 NM Push Device 137 Driver CIP j 500 6 NH NM 5 Push Device 139 Driver CIP ! 510 5 700 , 650 Cut, Pushed J 140 Driver CIP }490 7 700 l 650 Cut, Pushed J 142 Driver CIP 490 7 450 50/20 Push Device i 143 Driver CIP 500 7 75 r 5 Push Device 146 Driver CIP 475 NM 250 NM Push Device l 147 Driver CIP 450 5 350 NM Push Device j 149 Driver CIP 400 NH NM Push Device 150 Driver CIP 450 NH NM Push Device i 152 Driver CIP i500 l6 490 30 Push Device ] I t 4

e 908909 N/C Table 4 (continued) Maximum Force at Removal Attempts (1bs) Method Hole Fuel Cured Spacer of Substaining of No. Array By First Max. Force Second Third Force Monitor (s) Removal j 153 Driver CIP 140 6 NM Push Device Cut, Pushed 156 Driver CIP 500 6 700 3 157 Driver CIP 490 4 700 Cut, Pushed 159 Driver CIP 500 , 5 700 Cut, Pushed l 160 Driver CIP 510 7 225 5 Push Device i 162 Driver CIP 475 j 6 150 50/5 Push Device 163 Driver CIP 490

6 700 l

Cut, Pushed 165 Driver CIP 500 NM 700 Cut, Pushed 166 Driver CIP 550 NM 550 NM Push Device l 168 Driver CIP 550 NM 300/650/100 Push Device 169 Driver CIP 490 5 550 350/100 Push Device 172 Driver CIP 110 {5 550 5 Push Device 173 Driver CIP 550 5 NM Push Device Push Device 175 Driver CIP 510 6 350 5 CIP 525 7 300 5 i Push Device j 176 Driver l 178 Driver CIP 450 7 700 115/5 l Push Device 179 Driver CIP 500 7 250 5 l Push Device m 182 Driver CIP 490 5 400 30/15 j Push Device 183 Driver CIP 490 6 350 NM j Push Device 185 Driver CIP 650 i NM 100 Push Device 186 Driver CIP 510 ' NM 750 Cut, Pushed 188 Driver CIP 145 10 Push Device 45/5 Push Device 189 Driver i CIP 110 CIP 520 5 650 5 Push Device 1 191 Driver 192 Driver CIP 525 6 650 5 Push Device 194 5 CIT 500 650 4 Cut Out l 195 5 CIP 75 !5 NM Push Device 197 Driver CIP 450 7 260 l Push Device 198 Driver CIP 490 6 650 10 t Push Device' 200 Driver CIP 500 i5 750 700 Cut, Pushed l

908909 ff'/C Table 4 (continued) Maximum Force at Removal Attempts (Ibs) Method Hole Fuel Cured Spacer of l Substaining of No. Array By First Max. Force; Second Third Force Monitor (s) Removal 1 i 201 Driver CIP 490 NM i 350 i 50/10 Push Device j 203 3 CIP 90 6 i NM Push Device i NM Push Device 204 3 CIP 300 5 e 905 Driver CIP 500 7 650 5 Push Device 207 Driver CIP 250 NM Push Device 209 Driver CIP 500 7 400 25/5 Push Device 211 Driver CIP 515 4 i 650 650 Cut, Pushed l 212 i 5 CIP 515 4 650 800 ! Cut Out I 214 ! 5 CIP 500 4 650 700 i Cut, Pushed i 215 Driver CIP 490 5 300 NM Push Device. l 217 Driver CIP 475 7 let NM 1 Push Device 218 Driver CIP 480 NM 600 NM Push Device 220 Driver CIP 490 7 700 700 Cut, Pushed ( 221 3 CIP 500 10 Push Device 223 3 CIP lic 7 NM Push Device 224 Driver CIP 490 5 750 ! Cut, Pushed 226 Driver ' CIF 500 7 650 l 15 Push Device U 227 Driver CIP 520 4 650 700 5 Cut, Pushed 228 Driver CIP 510 6 450 100/10 1 Push Device 230 5 CIP 500 3 650 700 l Cush, Pushed 231 5 CIP 500 3 650 700 Cut, Pushed ] 233 Driver CIP 490 6 250 NM Push Device 234 Driver i CIP 500 6 1 550 10 Push Device 236 Driver ! CIP 480 NM 400 l 50/15 Push Device 237 Driver CIP 490 7 525 i 15 Push Device 239 i 3 CIT 500 750 i 4 Cut Out 4 240 !3 CIP 110 4 l 2 Push Device 242 Driver CIP 480 7 750 Cut Out 243 Driver CIP l125 NM Push Device 245 Driver CIP i 500 5 650 850 Cut, Pushed 246 Driver CIP 500 4 700 Cut, Pushed 248 7 CIT 490 650 4 Cut Out 249

7 CIP 510 6

550 250/5 Push Device

908909 N/C Table 4 (continued) Maximum Force at Removal Attempts (1bs) Hole Fuel Cured j Spacer of j Substaining Method of Max. Force Second Third Force Monitor (s) Removal No. Array By First 251 4 CIP 490 6 600 5 Push Device l Push Device 232 4 CIP 60 1 NM Push Device 254 Driver CIP 490 4 j 550 400 NM 5 700 700 Cut Out 255 Driver CIP 490 1 257 Driver CIP 500 7 i 750 i 125 5 Push Device 258 Driver CIP ,490 7 500 l 10 1 Push Device 260 Driver CIP !500 '6 l 450 10 Push Device 5 j 650 700 Cut, Pushed 262 Driver CIP ,490 7 263 7 CIP 490 4 650 700 Cut, Pushed Cut, Pushed 265 7 CIP 490 5 650 700 4 650 4 t Cut, Pushed 266 4 CIT 490 l Push Device 268 4 CIP 160 ' 1 NM 269 Driver CIP 480 7 l 550 15 Push Device l 271 Driver CIP 450 NM l 550 700 10 Push Device 272 Driver CIP 490 5 750 110 NM Push Device NM Push Device 274 Driver CIP 100 3 3 275 Driver CIP 510

• 4 l

650 650 Cut, Pushed 276 Driver CIP 480 6 425 NH Push Device 650 700 l 278 7 CIP 450 4 t Cut, Pushed 279 7 CIP 510 NM 700 Cut, Pushed 281D 2 CIP 700 Cut, Pushed ] 282D 2 CIP 700 l Cut, Pushed 284 Driver CIP 350 4 2 Push Device 285 Driver CIP 500 7 450 200 Push Device i Push Device 287 Driver CIP 110 7 5 I Push Device 288 Driver CIP 75 4 5 290 Driver CIP 490 5 400 250/50/5 Push Device 291 Driver CIP 510 6 500 50/5 Push Device 293 Driver CIP 475 6 700 Cut, Pushed 294D Driver CIP 700 Cut, Pushed 296D Driver CIP 700 Cut, Pushed 297 Driver CIP 145 7 50/2 Push Deiice 259 Oriver CIP 100 5 10 Push Device 4

90890h N/C Table 4 (continued) Maximum Force at Removal Attempts (1bs5 l Method Hole Fuel Cured ' Spacer of Substaining of No. Array l By First Max. Force Second Third Force Monitor (s) Removal l j l5 I I l5 Push Device 300 Driver CIP j90 120 '6 ' NM Push Device 302 Driver CIP j450 fNM Push Device 7 304 Driver CIP 305 Driver CIP l510 NM 650 ' NM Push Device 1 Cut, Pushed 307D Driver CIP l700 308D Driver ! CIP l700 Cut, Pushed 310 Driver CIP l105 6 5 Push Device 311 Driver CIP i 80 3 2 Push Device 313 Driver CIP 75 6 2 Push Device 315 Driver CIP 75 6 NM Push Device 317 Driver CIP 125 7 NM Push Device 318 ! Driver CIP 90 6 NM lush Device 320 Driver CIP 100 5 10 Push Device 321 Driver CIP 110 6 5 Push Device 323 Driver CIP 150 1 2 Push Device i i l 1 I

908909 N/C Table 5 Measured FTE-2 Fuel Rod Macroporosity Rod: 13 rod of hole 44 Calculated Composite FaggFlugnee i Photo _# 10 n/m Macroporosity (%) 1 1.9 13 2 1.9 21 3 1.9 33 4 1.9 30 5 1.9 19 Average ?.3.2 +- 8.2 i 1 i f I e 55

908909 N/C Table 6 Meta 11ography Results Attribute ThC (Th,U)C 2 2 Number of Particles 184 275 Kernel Migration (%) 0 0 Kernel Extrusion % 0 0.73 Buffer Debonding % 73.91 85.45 Fission Products in Buffer (%) 0 0.73 Buffer Failure (%) 50.54 1.45 IPyC Debonding (%) 1.09 1.09 i Fission Product in IPyC (%) 0 0.73 IPYC Failure (%) 1.09 1.09 SIC Flaw (%) 2.17 1.09 Fission Products in SIC (7) j 0.36 0 sic Failure (' ) 0.54 0.73 OPyC Failure (%) 0 0 Total Coating Failure (%) 0 O i i O l 56 -n-

908909 N/C TABLE 7 COATED PARTICLE ATTRIBUTES OF FSV FUEL TEST ELEMENT BURNUP SAMPLES Batch Identification 4161-01-031 ") CT7A-1015-A-L(b) I Kernal nC Type UC2 (8.2 ) 3 Density (g/cm ) 10.9 74 Mean diameter (um) 203 (c) Coating Type TRISO TRISO Buffer Thickness (um) 87 (c) Density (g/cm3) 1.26 (c) Seal Coat Thickness (um) 5 None Inner PvC Thickness (um) 28 (26) Density (g/cm3) 1.91 (c) OPTAF(d) 1.14 (1.16) Sic Thickness (um) 29 (25) Density (g/cm3) .2 (3.2) outer Pvc Thickness (um) 38 (35) Density (g/cm3) 1.80 (1.80) I OPTAF *} 1.11 (1.12) Tots 1 Coated Particle Total coating thickness (um) 162 (c) Mean diameter (um) 536 (c) Density (g/cm3) 2.41 (c) U Metal loading (%) 20.81 None Th Metal loading (%) None (c) i Coating Race (um/ min) 3.53 (3.15) (*}Also identified as E1391 BLSL 1-W I }All values represent typical values selected from some batches that i went into this composite batch (*}Not determined for composite batch (d)0ptical anisotropy factor 1 57

908909 N/C Table 8 Neutron Fluence Monitors e NEUTRON FLUENCE MONITORS Nuclear Reaction Half-Life Maximum Dosimeter Form (Type) of Product Temperature stable 1400'C 51 (, )52y 52Cr Vanadium 99.9% pure, 15 mil y (0.38 mm) diameter wire (Thermal region) 59 5.24 years '1400*C Vanadium-cobalt V-0.216% Co alloy, Co(n,y) Co 15 sti (0.38 mm) (Thermal region) diameter wire 54,g,,p)54Hn (Fast-313 days 1400'C Vanadium-iron V-0.522% Fe alloy 7 (88.25% enriched in region, threshold 54 e), 15 mil (0.38 mm) 1.5 HeV) F diameter wire. 60 Magnesium oxide-Hgo-12.3% Nio (99.8% H1(n.p) OCo (Fast 5.24 years 1400*C nickel oxide enriched in 60N1), region, threshold 20 mil (0.52 men) 2.7 HeV) diameter rods. D e 58

908909 N/C TABLE 9 MONITOR RESULTS II FLUENCE FIMA AIIAL MONITOR f LOCATION FAST HOLE f (IN.) (x1025) UERg) FISS M FERTILE (x10 MONITOR #1 2.6 1.6 3.8 45. 1.0 HOLE 18 MONITOR #1 2.6 1.6 3.8 39. 1.0 HOLE 67 MONITOR #1 4.0 1.6 3.7 47. 1.1 HOLE 301 MONITOR #3 21.5 1.8 3.7 48. 1.1 HOLE 86 MONITOR f4 30.2 1.5 4.1 49. 1.2 HOLE 131 MONITOR f4 30.2 1.6 4.0 56. 1.2 HOLE 239 AVERACE 1.6 3.8 47. 1.1 STANDARD DEVIATION .1 .2 6. .1 (1) PIMA is Zissions per initial heavy getal Atom. FIMA was calculated using this formulas % PIMA = 100

• D/(
• CF*PY*A)

Where D= DPM of Cs-137 per milligram of initial heavy metal = decay constant for Cs-137 = 4 368*10' CF= Correction Factor for decay and depletion of Cs-137 during irradiation (CF = 0 95 for U and 0 97 for Th) FY= Cs-137 Fission Yield = 0.062218 for U and 0.068038 for Th gg A= Heavy Metal Atoms per milligNas (A= 2 5613*10 for 935 enriched U and 2 5961+10 for Th) The initial heavy metal loading was calculated using this formula Loading = (4/3) * (D/2) *

• WP Where D = Diameter of kernel 3

= kernel density = 10 9 mg/mm for UC2 and 8 74 for ThC ) 2 WP = Fraction of heavy metal in kernel (WP = 0 9073 for UC2 and 0 9062 for ThC ) 2 59

908909 N/C Table 10 Test Specimena Machined from Test Element FTE-2 e Specimen Specimen Number of Diameter Length Specimens Tvoe of Test (in.) (in.) Orientation per Face Tensile 0.22 1.25 Axial 6 Transverse 6 Thermal 0.22 1 1.05 Axial 2 Expansivity l Transverse 2 i i Thermal 0.375 0.08 Radial 3 Diffusivity ) f I I i I 60

908909 N/C Table 11 TENSILEPROPERTIESOFIRRADIATEDH-451GRAPHITEFROMFTE-2 ORIENTATION--AXIAL LOCATION--FACE-A BILLETNO. SPECIMENNO. TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa) STRAIN (%) FTE-2 4A 28.1992 0 0 FTE-2 4B 28.7083 0 0 FTE-2 6A 24.0631 0 0 FTE-2 6B 21.1912 0 0 i FTE-2 2A 19.3378 16.004 .124157 l NEAN 24.2999 (6.004

o. l2gs7 STD DEV.-

4.15275 ~ ORIENTATION--AXIAL LOCATION--FACE-B BILLETNO. SPECIMENNO. TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa)STRAIN (%) FTE-2 2A 25.4638 16.6168 .158642 FTE-2 2B 22.1839 16,7126 .138024 FTE-2 4A 24.2194 16.7054 .152204 FTE-2 4B 27.0363 16.4175 .176573 i FTE-2 6A 26.4571 15.8412 .178045 FTE-2 6B 28.7746 16.441 ,188374 MEAN 25.6892 16.4558 .16531 STD DEV.- 2.29881 .326746 .0188772 61

I 908909 N/C Table 11 (continued) TENSILE PROPERTIES OF IRRADIATED H-451 GRAPHITE FROM FIE-2 ORIENTATION--AXIAL LOCATION--FACE-E BILLETNO. SPECIMENNO. TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa) STRAIN (%) FTE-2 2A 25,159 16,7081 ,165305 FTE-2 2B 20.8918 16.2656 .131618 FTE-2 4A 22.4683 16,6297 .144356 FTE-2 4B 26,4481 16,9506 ,167483 FTE-2 -6A 28,4602 16,6325 .183771 FIE-2 6B 28,5949 17,8085 .172823 MEAN 25.3371 16.8325 .160893 STD,DEV.- 3.15034 .526171 .0192826 ORIENTATION--AXIAL LOCATION--FACE-F

BILLETNO, SPECIMENN0, TENSILE YOUNG'S FRACTURE' STRENGTH (MPa) MODULUS (GPa)

STRAIN (%) FTE-2 EA 23.6294 16,927 .146122 FTE-2 2B 21.1324 16.5164 .132159 FTE-2 4A 20.4641 16,7647 .127196 FTE-2 4B 16.0678 16,6927 .105999 FTE-2 6A 23.3045 16,7988 ,141393 FTE-2 6B 22.0689 17.0203 .135401 HEAN 21.1112 16,7866 ,131378 STD,DEV.- 2.75406 .176915 .0141144 62

908909 N/C Table 12 TENSILEFROPERTIESOFIRRADIATEDH-451GRAPHITEFROMFTE-2 ORIENTATION--TRANSVERSE LOCATION--FACE-A

BILLETN0, SPECIMENNO, TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa) STRAIN (X)

FIE-2 IB 25,1827 15,4053 .182769 FTE-2 5A 24,8229 16,3006 ,172627 FTE-2 3B 20.02 15,4327 ,153096 FIE-2 7A 23,7758 14.2444 ,178782 FTE-2 EXTRA-A 23.0111 14.5539 .168264 FTE-2 EXTRA-B 21.0774 15.2652 ,144193 22,9816 15,2004 .166622 MEAN STD,DEV.- 2,06222 .726974 .0150559 ORIENTATION--TRANSVERSE LOCATION--FACE-Bi

BILLETN0, SPECIMENN0, TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa)STRAIN (%)

FTE-2 1A 20,9754 14,755 ,154229 FTE-2 5B 19,0726 13,9433 .143707 FTE-2 3A 21.5107 13.5844 .173194 FTE-2 3B 21.219 13,9018 .16107 FTE-2 EXTRA-A 16,0968 13,4821 .125632 FTE-2 EXTRA-B 20,7922 14.3588 .152307 19,9445 14,0041 ,15169 MEAN -STD,DEV-2,06998 .480122 .0161245 63

908909 N/C Table 12 (continued) TENSILEPROPERTIESOFIRRADIATEDH-451GRAPHITEFROMFTE-2 ORIENTATION--TRANSVERSE LOCATION--FACE-B2 BILLETNO. SPECIMENN0, TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa)STRAIN (%) ~ FTE-2 3A 25,9152 14.5159 .194492 FIE-2 5A 22.6406 14,7419 .162345 FTE-2 5B 21.9965 14,0738 .162086 FTE-2 1A 20.043 13,6738 ,148843 FTE-2 -EXTRA-A-23,7846 14.5567 .177482 FTE-2 EXTRA-B 21.9929 14.2199 .162091 22.7288 14.297 .16789 MEAN STD,DEV-1,97823 .389279 .0158777 ORIENTATION--TRANSVERSE LOCATION--FACE-E ~

BILLETN0, SPECIMENNO.

TENSILE YOUNG'S FRACTURE' STRENGTH (MPa) MODULUS (GPa)STRAIN (%) FTE-2 1A 19,8627 14.1312 ,144147 FTE-2 iB 24.7069 15.075 .174765 FTE-2 3A 22,6227 15.2037 ,159086 FTE-2 5A 16,8188 15,002 .116694 FTE-2 5B 22.6428 14.4385 ,164308 FTE-2 EXTRA-A 23,5963 14,9763 .170115 21.7084 14,8045 .154853 MEAN STB,DEV-2.88369 .42147 .0214825 i 64

908909 N/C Table 12 (continu'ed) ~ TENSILE PROPERTIES OF IRRADIATED H-451 GRAPHITE FROM FTE-2 ORIENTATION--TRANSVERSE LOCATION--FACE-F BILLETNO. SPECIMENNO. TENSILE YOUNG'S FRACTURE STRENGTH (MPa) MODULUS (GPa) SIRAIN-(X) FIE-2 1A 24.2083 14.2271 .188753 FTE-2 iB 22.3593 14.0052 .171287 FTE-2 5A 20.4758 13.7394 .160841 FTE-2 - 5B 14.353 14.2241 .104971 FTE-2 3A 20.576 14.9092 .151347 FTE-2 3B 12.746 14.0315 .0976072 19.1197 14.1894 .145801 NEAN STD. DEV.- 4.55398 .395532 .0367182 i l 65

908909 N/C Table 13 Sumary of the Tensile Properties of Coupon Specimens of H-451 Graphite from Fort St.-Vrain Test Element FTE-2 Tensile Strength Young's Modulus, Fracture Strain Orientation Face MPa(+ std.dev.) GPa (+ std.dev.) (+ std.dev.) Axial A 24.3 1 4.2 16.0 0.124 B 25.7 1 2.3 16.5 1 0.3 0.165 1 0.019 E 25.3 1 3.2 16.8 1 0.5 0.161 1 0.019 F 21.1 1 2.8 16.8 1 0.2 0.131 1 0.014 All Faces 24.1 1 3.4 16.7 1 0.4 0.151 1 0.023 Design Data Manual 27.2 1 4.2 ,18.6 1 1.6 Transverse A 23.0 12.1 15.2 1 0.7 0.167 1 0.015 B (Set 1) 19.9 1 2.1 14.0 1 0.5 0.157 1 0.016 B (Set 2) 22.7 1 2.0 14.3 1 0.4 0.168 1 0.016 E 21.7 1 2.9 14.8 1 0.4 0.155 1 0.021 F 19.1 1 4.5 14.2 1 0.4 0.146 1 0.037 All Faces 21.3 1 3.1 14.5 1 0.6 0.157 1 0.023 Design Data Manual 21.7 1 3.8 15.8 1 1.3 e 66 .~.

908909 N/C Table 14 Thermal Expansivity (25-500'.C_),of, coupon Specimens from Fort St. Vrain Fuel Test Element FTE-2 (H-451 Graphite) Axial Transverse -6 Face Specimen No. CTE(10 C-1) Specimen No. CTE(10' C ) ~ A 6B 3.79 7A 4.48 8A 3.79 B (Set 1) 8B 3.50 7A 4.38 Extra A 3.77 Extra A 4.53 B (Set 2) 7A 4.51 7B 4.60 E 8A 4.15 7A 4.64 8B 3.87 7B 4.57 F 8A 3.96 7A 4.62 8B 3.89 7B 4.62 All Faces 3.84 1 0.19 4.55 1 0.08 Design Data Manual Value 4.'59 1 0.32 5.38 1 0.35 i e a 67

908909 II/C 8.182

% g SOGSOOSON k

IA 02) CCOLANT HOLE C 0.500 OIA (6) O*c,060 eeSoo e Oo e ^' C *i G .r0 14.172 60 EO O DIA g 0 0.740 0 C g g PITCH SGG FUEL HOLE fi G 6 \\4 0 $00'iO 0$O[ CEHENTED o GRAPHITE FUEL HANDLING bA.7jg PLUG (TYP) PICKUP HOLE 1 IN. CLEARANCE f \\ 00WEL PIN 7 !Q%fMEl3i I! 7, x i ~ g [

,g{ [ ; { [

/ 15 lN. $ l [hj \\ , HELIUM ) FLOW (TYP) 4 1 s s f h g l j l j 3i.22 gj BURNABLE 7 g$[b k i ! E 3 3 CHANNEL '/qi g { { { j! CCOLANT h l FUEL R00 '\\ 29.5 IN. y h [) t 0 [ t : s LENGTH $4 fj k h. { { { ?d)ia!! !E!M$i p 88EST SEc ^-^ Fig. 1. Standard FSV fuel element configuration. 68

908909 N/C DOWELS FACE E i s \\ 5 A x\\cw \\ Q \\ '5.) %j' 0, 9 4 4 e \\ HANDLING HOLE ,/' l +0 40 Ap V t ' ',. TQ o 4 i FACE B l i I l l r e J Fig. 2. FTE-2 Side face identification. i i l l l l 69 i--en--ww-e-u,9-ww v p, w g--r m-m __--myem-g-wem r-N-7w 'w--'

903909 N/C 12.65 MM (0.498") SEE PLUG I '\\ l DETAIL BELOW~ \\ / l ( ' nfK \\ = T 'V 6.35 MM (0.25") 12.43 MM (0.4895") DIAMETER 49.28 MM (1.94") LENGTH -15 RODS (STANDARD LOCATION) 14 RODS (DOWEL LOCATION) / TYPICAL POLYSTYRENE t % ' WAFER 12.50 MM l 3.84 MM (0.151") (0.492") (STANDARD LOCATION) DIA. M [ T

g

$'?;;..N!S2S* i?q.N,.,. ...I. : E 6.35 MM (0.25") M;W'h.c. v PLUG 4-Fig. 3. Fuel rod configuration for cure-in-place assembly process. 70

"= g i an m. 3 a e 55 = a -a te s2 3 l ! !~B3 ! Eh a!$! = g g 8b x2S b 23g E e".!,g 8 o i B.d o~ ! .2 3"3 o e e m. n 3 - = 333 5 5a a=9 os . o3N-go o .on-0 Els*a s$ h D eg y -O N Eig"!=2,p o ~ 0 e: O O ! 88) oO@0 o0$ 8 !!! I 8 o e O 80 s BE 0 00 l O 0 0 00 O ) O 15, 3 6 @6@GO o@_, o o aa y a O" O 8 O O O ig eg te @gg!8 g 80 ego ia, ee !!i o i s is O u*s

e s

88 555 /. 5$ ^h 52 aa a o mu <5s sw5 E da E "W 3 $ $ E$g o oi EE*$5 3 5 $$8 8 8 E ,g'so t =

o

a a g %20v m l .. < E i a ' t; oIci d U $ 5$ E 0" 3 $ c e setas s 8 eme r g an. o -= ~ e-o o -- m no e,8 e 1 l l 71

908909 N/C Graphite Tube (FIMA Monitor) sic Rod (Temperature Monitor) / " /,/ \\NNANNIs\\\\\\\\N s 9 wow. pen ~>ygg-GRAPHITE j. ws ss s s- . s s sis x s ' N NN 12.42 mm $x + (0.489" CRUCIBLE ,, m,. . _ s s,, A 3 __ i- /g-- //////A\\' \\\\\\\\\\ \\\\s\\\\N\\'i o L,, 24.64 mm

. Niobium Tube 1

@ @s 4 (0.97") (Fluence Monitor) A Graphite Crucible (Section A - A) 00SIMETRY WIRE (( f;. hNtem.~m--cm:c5q~} / N10BlUM TUBING FUEL PARTICLE HOLDER ITDI MATERIAL l. Temperature Monitor Silicon Carbide Rod 2. Fertile FIMA Monitor ThC TRISO Particles 2 3. Thermal Neutron Vanadium Monitor 4. Thermal Neutron Vanadium - Cobalt Monitor 5. Fissile FUfA Monitor UC TRISO Particles 2 6. Fast Neutron Monitor Vanadium - Iron 7. Fast Neutron Monitor. Magnesium Oxide - Nickel Oxide ~ Fig. 5. Schematic diagram of monitors used in FSV fuel test element. 72

908909 N/C h Holes with monitors OOOOObOOOOO ev 2" tea gO O -O OP O!O @O OOOO O leOOO gg O i OO O OO _/ g O O O OIOOOO O OO O O OO O OO Monitor Count Holes Monitors Total 7 x 4 28 8 x 1 8 36 FTE-1, -2, -3, -4, -6, -7, AN D -8 ALLINDICATED HOLE LOCATIONS HAVE A MINIMUM OF ONE MONITOR AT TOP OF ELEMENT FOR ALL FTEs EXCEPT HOLE LOCATION 248 HAS FOUR MONITORS (FOR ALL FTEs) ANO HOLE LOCATIONS 59,86,131,194,239, ANO 266 EACH HAVE FOUR MONITORS FOR FTE-2,-4, ANO -6 Fig. 6. Radial position of monitors. 73 l

608606 N/D i i E6'01 C6'It g6'OZ ts ni pr

:s ti ti rt I3'lE

- ts as ti.6 F !C sl u-t5 06 ts Ds - ti :6 e _ ts er \\ ts 02 !402'% !c c.

t er

s et tini

5 0:

C6'07 C6 g un c ' ti p I"s' :s er "g' I"rc' En ot t:ot f5 E' 8 tt es rg t tc:

• o...s :

ts:s tr os te is tt 0T

• s Dt ti Ct ZC 0t n is tios ts et tt el tc:6

s tt nI

s'DZ 26 3Z E :Z

!t ;Z '-:i i: C6 rt g,, tt ez is ez tl et

s ot ti ot nn

ut

s ot g eg ti ot ti ot tS'DS I8 38 tees

' ' g' ' ', g ' O

ot

~ riug g3 dn ~ ts: g i >s s et 3s a

s os

t is tt at

t

t ot

s':t ti ot - ' t'.Z...:.4 rt is - -

te pS ne DE

s ol 0: 05 ri DS tt er

4 ot n:02 tr oZ ts oZ rt cZ T ",

-= Zt ot '.t.i.. ",o' - tt at isot u ni ot ot cs ot rZ GL tt i s tt at is ot et ot or ot es et I6 CS tSrD "gg# ' "a 4 g "g"

• C'g '

l

gg 4.Z..Z. Q. 13s ciDs 0t 0s ts 3s t ttis 't os tt et n a ct ts er

!ot cs ot rZ ot

'!t tt 36 si 05 01 DE gz UI 0s 0$ ZZ 01 4:s U CI is eZ cs ot ot cr ot Lz .e cI rt eZ tt C1 is et esoz ti 04 CC C: ac 01 !!01 g7gg

, gg 0s Dt g, gg i

E Di 0 01 Q Ci Ot Dt ,g gg CG .H,s 0.t C5

t C.

~ I 6' t 6 II .s E ~ sses s 8' " CC " U 82 rt i t tr et is et

s et ri ot ot ct

c ot

t :r L

rZ 05

s 05 0: 25 04 01 tt 5

0 05

!t 0l g ! 06 'Z I { t7:5 ti ct inr DE DZ cr 0Z .s 02 N 1 S tt at i504 \\ 05 01 07 04 .i ot !t 04 ti at ti ot il ot ciot et er n ot r-ti ni

'g

",8 ' "g 05 g 19 ti m I' il os , :a g es . t es 7t: , s is 06 09 ti.6 ti ct il Ct tl et ot 4 4 ce Zt ot ti 05

6 05

t 05 ti ;$

tf 05 4 + ti sE !C OZ it 0Z ' 1el iZ CZ

5 GZ

\\': 6'1 '.'t,,s"r ( 04 .ICi ar cs g,, !C 0t e st ., g ,t et tt,ti .t,o i i t, g g,l e. ca ';:i = :s ot g .g a :i,, I6'il

ees

.t as it s .Z E iZ 3r \\ :l E

c.s a-tt et it ot

l c.

E676 c nE ir eS .t :5 .Z :5

l ci

s oZ 7== q tg il

s nI

s ol

i. >

s ne rt ci

s ez 5.t a

T ~. "e' ?s or\\ ?s oL I"re'\\ s et !"g ' "g '

31 t

tt

s et -

8 t6'19

83s 3 88 rios

!s E ts u C610 3 T :s at ?s 0t !4 CF ?s tt =

6 :6 csi 24 :6

s:5

_ S " c il $ :s il C6 tS

• :s it C611

[ N ts op I6'!t I6'lZ C6'1C ? dlE-I

5 04 dTl9 413-5

0Td 09 d13-Z Z209'd 09 d13-9 10'OL'd 09

OW'd d13-1 05'05'd 09 d13-t ZL'01d'09 813-t 09 d13-9 OS'09'd 09 3T t-ao2a dosT3Tous )geXa2 9( syonIuS I03E3Tou oJ oT qa aasa eIamauas-3 2

L4

908909 N/C l a hNi '~4my n- ~. y,%- s j V. c i;;, i gy ; + . a vn.,;, [ ffs.:;9: = p %+ {l: '. < hkk

4QQfw f'*

f <.( L& :. .u,. . ;~ ~ fh, g,g,,

FTE-2 g-.

a', 2Qg i ~, [) '4; 68t0&O_6_ i VN2:fositos wbn.. s &wdzihlW" w luf? f. _ ' 4 -;. ' ,; r: *:

^t ~

'.

p. ~> ri. y:n ^ g

• f'

- 1: 1 J< ' V,. a. t 4 p bMP1..._. Fig. 8. Side face A (taken at HSF of FSV) l l 75

908909 N/C 7..,....,.. 1-a 5 ?, t: ~ p lp,, l,. c_ y, 44 g-q<:,' - l kh i5

3..

e h s%g ~.~ y y:n ge: l .se t.v-g;

c. ~

, y f;_-

c y

5. fu n' _ W Q..'* .?* gy, .Q :' - Q._ f;;y y,c - ; --g 2 y s. -e. ,4.. g _' D,. .-~ ~ i .7 l Dr jI .! t r - 4 -($m. k%~, kl A .c _ S~q/:= - .;g ;Q, 1 2 n l &. ; -;c . : /, g:' QyQ m;. iW; J. lf:l bA Fig. 9. Side face B (taken at HSF at FSV). l 1 76 1 I = ~ ' - ' - - - - - ' ~

l 908909 N/C D I. t + D

h. -

v. [.; e,...,j ,t y r. i i-Ttt:%n. r-t 4E:_."'i M g M T, ?) ;. ; ^lMl*f[yx 'Vy ;gg%1* (. c ; y. ; > - jj,., s,3., p; y, ffgg - ~ --~ .,y Tt$ ' / + E', Ts: $ ?^%jf}lT;? f;l, ;hy:;, ' i; y;$ Qi 2 'g if- 'j: r:

n. :W :[y$

' f [' [ " D-) (){J' %. ' y :.y - C;' r gi. %.:a.: ' { ' ~ *- o} ~[, y ~ h, :':n:, n;i.

;;): -

_. sg,~.

~='.., ~l ?y l,- y, Fig. 10. Side face C (taken at HSF at FSV). 77 r

908909 N/C 7:_~:a=. t ;,, 6 e- - j p.;.i. t_ l . m. l$;4:M,Q:

1. )

A% ~ ' .x., :;,;l?, i-w ,-( \\ h i ( ( v ..S lW:,,:,.-.,,. -c.

~'

y nN @t; i - 4 ;,':..., .g.4 $+,.. s, ~ 3 9 s A 2:o:pf y, l:, gEc l + . et 38k

g. ?

l 'a l ,w. 1 Fig. 11. Side face D (taken at HSF at FSV). l l l 78

908909 N/C pmm m i. - i-li k:c )): <. b

y.,

{_l n -;&aQ-.C4;- 3:e f _ f,qA' e 3: ;-.~ ; ~ p-x.; 5 t 5?. ,. ' s ~; :.':hSS%'~ i! y - ~ .g_n, A!cpily? 111.c4; ^ 't i ,;. g.c ($c? g ,3 ; 3'].

r te- %;.,...

g} ;

i n .e

= " m: :im -

~ Fig. 12. Side face E (taken at HSF at FAV). 79

l J 908909 N/C l 4 s- ~ 7., _ m-,.,.-- -S ,3 h., .y :. is:, g. m, v. iv, i; +, + .,C 5, ? 'i ~ e t.:..: v g 1-7: ) e A5'.c (('.y' kk E ...c-

,.:;5 ~

y 4 "%-lll "l ?: - Wi 5 %,:., m!' 3 W p'; - t Vid -. ,.Nck. e-et [. e,-,5D L '.. - < s 3,. c%- 7.; ,'. Q E' N q 1:;3 r. ;0 ~ t cy CW .se ;.; ' j7h', j

g

; - ~;

g f.,,

-. 3P7 r

y...

' ~ a. t- - ,? w '1 m v e:-]: 'e '~. , 4' m .y ., ;e y y.. ~

= Qe,l?

v.s., p' % - my.en... l Fig. 13. Side face F (taken at HSF at FSV). 1 80 1

908909 N/C i P Ek. I ~: I .t .; r '~ki fyl,

.4

. g_-,.>:;,J' S L.- s ,s Fig. 14. Stains on top surface. 81 l

908909' N/C 9 FUEI. ROD STORACE STAT 10R llIGli LEVEL CELL BOTTOM / \\ CUTTING STATION 6 r i 3 l BAND SAW l aa g l AND CRADLE l q l VIEWlhG GRANITE TABLE WINDOW 5 g g l l J l - ROD i3 15 \\ ll l "I FutL ROD PUSHING AND FORC DUAL TUBE l HEASURING STATION g RECEIVING TROUCil l WORKBt.NCll. TOP OF FLEMENT h BOTTOM OF ELEMENT l. / f FUEL ROD PUSillNG l_ ; , _;.g ; 9e AD BLOCK 8-0206 ROD l' y ROD' 1 FORCE HEASURING 15 \\/ STATION OPERATOR 2 AT OPERATOR I AT VIEWING WINDOW 3 VIEWING WINDOW 4 Fig. 15. Ilot cell work stations. 8

4 908909 N/C l 0 ~ 0 44Rr44lW p >. - Ng, L; 'c' , ';.s '7', ,9" a- . v., 4R'- ,,. y -f ' 2[:y. s $g,..,e . y; E' , ';f 4 lll ,f 1 'fyg.e p t. 3, - 3

o e.,i, t.

s- , w,, ... w M sthN$ Nt.h

1. 2:#

1 Fig. 16. First cut from FTE-2. o I I 83

908909 N/C ss % d ~ FUEL HOLE PLUG T...> M

• iks. ',

'#' h I' zgj 'y* g d (1 REQUIRED) m +a

:+:![

$$gj 13 12 11 hx

i?%

10 ,s ^si., , g ,pTEMPERATURE AND FLUENCE MONITOR . so'~ h 12.421 mm (0.489 IN.) DI AMETE R , Il! j;ij!)i 2 v.!::- 3., l I -!!$hfi[( ..s \\ !$li 1 !!!!!!!!!..:ifi9' !!!9 .~ $ sih +. -'. $.C.$ ,g

+,

~ Fig. 17. Monitor and fuel assembly for 4 monitor stacks. 84

-~ _ 908909 N/C .i ... a pg1 N '*f, o

g. h

, e' ' 0- . ;~ ;, 4 . _. }. ';k.,.,*-' ) :%Q U

' l

h.,

a &;.p;,- V' + l l .__.-s ~ - ~ js,' s' ,.t Q *+.. ?;f ' \\.$\\ ..,..,.-c.. ' 't. ! .,,I.' :. y,.. 1 [ Y.... \\ L y ,7, ', y.g,,f *..: f ^ ~ ',. .\\ ,;I.d.*?[7.Sf 0' s

a-2f; a M

-j n." a . s, I. .s if Fig. 18. Side face C damaged by hydraulic press (note fuel particles from crushed rods). l l 85

l 908909 N/C

p

,.I. s i 3 .g -.g x.n %i, 34 ~-['- Bondi ~ .pg n 'y' (This cut was made during a cutting out y operation) 4 .. '... ~. s . W 7 5 Bonding' 4 a Fig. 19. Bonding from CIP rod curing at axial location approximately 8 inches from the top of the element. 86

908909 N/C

1. ~,s c.

Recoved unfuelled side face fl~?."'7 c i ,g ot / Top ~ Et / ~ c ,i s,. _ ,,. a N 31.22 1 _ _ y l 7 inches 7 inches t

n Voo ~oo~~

\\ l ll l \\l! -l ~ Axial Cores Transverse (typical) I Cores (typical) i b! t..I {, (, 000 autto - (tv9 1c 1) Fig. 20. Location of test slab in fuel test element. l l 87 I

908909 N/C , v '.:.. ,ya. ... t b %.\\g- ' *. ll~ - _9y nJ CIT .'. '( %1. ,g" ~ M. A' / .J >s:;dk? ., _,..a n k s. ~ ,;g.X8t 3 l\\Ryp:.&'L'^ -n t: . s f A'.' ** L. ..., ;p b 5.,@SsG:,.,"y ': g/ -A jf,$? O.'?p%.' *A %.j dn n, x'[3 :g Qr.::=. s'- ' y

, $.u, bj' i :

4 c,- CIB 7 2"3;jg._WC s i

• gj l.4 3

, n., .: ~-1A L'M Fig. 21. Typical appearance of the CIT and CIB rods. 88 4 w_,,,,,,,

44 4 4 + r ,C x* N t~ we v f s,u xh g,%{W my w ~z ~ ,s Y{ ' ' 1

e. a

h@;y mxwnns., Nap w

A;k.3M, Y;s Q:*?n%h k( d* s f, c. %sd x +W.aby }glw'. J > f[Q: .[}h

~*

j ngs s 3 g % u:. w p. o f, ,L pa Q g,

• wpf1,,

. ?' i:y a, ?

tg4.4

'M ug9g ~ ((W,.. nf m%m, g?e f g

• ?

e f <.: ~ - e. n v, f2, s ~g:3 . fyfj; %/ n 3,

• x r iyg

~. ~' &w g \\ S g ^

Je N' L...

s, p y y y* ,D ~ -,,, s -~. y <3 .^ ~ Q y x p s s

• m s

5, ^s +:%. X \\ N 5' 3 N x g +f 4 y,k fb } sp 3^ \\ \\ g \\ 8 + S' c.4 @ $ e s%%' 4. 89

908909 N/C Stack 44 TOP l ' CGO 1 O 3 1 1 6 1 O i is 6 se (1 Rod used in l ?i metallography Rod 13 f i stack 44 I BOTTOM c., ,g,, s# y.. g h, } d i<

• 4 e.r.M Fig. 23.

Fuel rod used in metallography [FSV reference fuel: 90 (Th,U)C TRISO and ThC TRIS 0]. 2 2

908909 N/C i I l 9%Mg:y R";>.Js 7 c'y l 8 hy;,f k' .f,b .,...s y a>,.xtGn, m., Q } f ' I wg,. c '. ,,5. A w.1... - v.s 4 . p, yf, A. 4..m ~y v Ac~ c  ? r

v. +,,,/,.. >, '

f - y _.,;,; w - < f,, g*,1Q^ J ff' f, a4i . g.' h. + f ll. ,y,,s r ..t yll Q N~p lG.; ' $.. ; }..= ase ?[g' ;g,:&. J. g+ g,s>w %y.or,y :,]? g _ -/f . _. :.y,-:-;.=4p. 4. %, y w_ 's- ?- t ;.? ::-%y).N'.,Y$, u'ff,9;,(,,'3r>; -. #,_-5:.:j, f 4, -:, u ,1 . x s &.f 'W%' . h, s 'f A' c

• & 0*llIn6 y
• f4 ;4,

/* m % ,g v-, r; t 4 b */ y,u.,. Y.k Y e:4*?'r'. % d N.' cf. - ,4 <r' 30 pm i y' i ,,.y .j ^f; ,'( - + - ' /ps,,,, ', ,. &{<,.

• 4

~ a. .. +,_ ~ l t';,, (, [, * ' ',' b' ? ' ^ g ,> ? ; r - r s E y ~ -!^ , p.,. /,

g. : :.,

p.. lt . bf f /, ~. f-sy' . ? J.. t j, - ). 3 ~ .r . tA. ' / / k,

• s9 9,

i z ., k,, s. v.p, is. e ,s \\'.. ,,p' ~ f' f ', ' s. fy .l .'_} . t; g'. 20 pm Fig. 24. Photomicrographs representative of matrix phase of irradiated rod 13 from stack 44. 91

908909 N/C j 1 I .M M' ' \\ / g;,ge ,e .( gy i y 2 s ' M ;'

e e

) 1 - N.'. j. 25D 330 pm Fig. 25. Representative photomicrographs of composite of radial cross section of fuel rod 13 stack 44 (left side of rod). <, s

i, 908909 N/C 1 1 i' Y' ? ' W$ ' mt ' ~ ' ' s ?, \\ ~ ~ s d 9) (he,f[ge8fg, gy:a r l %gg e e i< 1 l 9o ~ I r.3. } o Fig. 25 (Con't). Representative photomicrographs of composite of radial cross section of fuel rod 13, stack 44 (middle of rod).

'908909 N/C i i l >Q- 'O ep;! og. i ). = I ,1 l u 0o l eg B j :oa Fig. 25 (Con't). Representative photomicrographs of composite of radial cross section of fuel rod 13, stack 44 (right side of rod).

908909 N/C [ n x ky 57;' RA ~,-:-T= 3

?

,.c,.. - Q.,.. :.,._.%. ^' ^'m sq. p 3 - .s n..y a . f. 4,..,.1 -% g %xA hJ '.,,'Q { \\ ,,jg, j;&h_ sMSi e.m :. '; y, $ 4{. S. hy: ~. f '4- + ' i r. - g c. . a. (i,. h ' i: -;;h:_ v " y*.

., h f/4(

i ' ; J4jM F"'.;y.. j 9)I.x -M,, J$9y@dWp:q*,. M (NOh n.:";6.2 M ,l'. j; ~ q rm wr 1.1&.Th; u v s

f. f.,

,j .h cM .') t 6[ p }g;Y~y. X3 y ,'p-6 U*1:M ~% t(;l . w w N %4.4}.. 9 -f ; w 4 ./ .. / j/.l< ' s. 's v" ..-i.J ;. 5.:- ~j ;(,' G f h' Q' g,ig & -j.g. (a) .. ;f h 4- ~.. -g c. T 4- ...n. \\, -(ff .*?l%' 'I ' ./.. / o. _ r;. w, p \\.l' '. ,f. \\- N.I 4 &g 'l ' %%,%t c.,k, '.?.rw l h 're j-i. 2,- o e a.- .3'e 1 d* \\ ehe d.i 1 :. ;'. I.- Ni;1-g*f g)r-.-L a. s../ + f 4,;.g2

.J!iN.

s oNs W&n$;hh.\\',NE;Y. ig.'f[ b w-f ](4h;sk i 4 ~ .2 100 um ~ hp % '~ (c) 'SNy 'r Fig. 26. Photomicrographs of typical fissile (a,b) and fertile (c) particles. (a) and (c) are bright field illuminated and (b) is polarized light. 95

~ 908909 N/C i l l l ,... Q y ' 'f ( %,' S,, }.+ g,j ' 3

, C M p. \\

N k.$ fl"5 $4.,' \\. , f, 7 ;x Fiss11e -{ ' '^ l t b, m) ) . s,. .p

,a

. m.e e -S \\ \\,.p', / i - 4... y +' gw -

f. 6

),y 3 AP--

% _, p A (\\ b,'.'[ '.gg.v% \\ a p 'N m- \\j MMJ' k .$y'r.~,,'fl.v.4.\\, - " 5. e .7-:;y$ N s

i.. ? i

' 't 3 i/

. c.

. 3. 6 "f .v.c+.;.: O te s lr i - ?,- ';j,.gy,T p Y,Ath Dt--Q. h i ?. ~n. ~ ,:- $ec - ja 3y p ;.._ - ,. 41 Fertile ) ~ ?- y S)k.. {. t it,, C e. l j.- '.' h e- < ,a, \\ j v.% ^ f. N &-

• y '< :

%s.. - e,y.- .w g.. lr%, n)4 '/ Pi~.* . %Wn.',) < %7 ;,- Mad- ^ o.*. ~ or. 45.. !+. I t l ~ 4# 100 pm . i ,j 74 100 pm (a) (b) - :c t..'- . n-p ' ?_ L p1'5 ,Q shu x g.y GW ' *...dV ,d .'N L

g... 1

,+ ~ l ,A' - 5:~ **; : - .g. Cp :.,

x.,

l A j. ~ K!%....e.,&. Ad.; \\qh 9'v ~ (r 7, eJ. - ig,I t-f - 'y4W'1_ @ff,- *h 0;< zb.

n. g r.w. -

i, K'p: - f , ?2 ~. 0 !$[ _ j' ] . )e. \\ lR, y.... ,9: l .,/,.7 .,, 0. s + ~,%m. ma--.7 e,. r 1:. e W =w-- _ q ~ ~ = p* 100 pm (c) Fig. 27. Photomicrographs of typical fissile (a,b) and fertile (a,b,c) particles. (a,b,c) are bright field illuminated and (b) is under polarized light. 96

908909 N/C ~:r_s' s,.y .... \\;p.7.y;.yy:y "W A..,. ,t. *:. j; Te p 3l .. s. r. p -s . t _.r.. s s _. .,.. p m... ~ a

p..;a m:h. g,.

S

._...w.- ' qt. .g .,- w % e :;!.J ' ff -

f. 3 W;. s 1

ft :' l.;:;*., . r ?.~p

v. a..

0 ]Jr.?. y 4 '. 'J if '

• L y

'h ,i j J.'s Q ,.,,"/ 71e vly?. '.,. ' ' - Q." ,~ .a r; s h 3 -em I ',,7 '. : - T r,.

s.

. /,a.., ..,i.* ;g;.... a jy g 3 r.,. ss

p; g4

+ L..; L

, y:_'; 4,.

l 70 pm l l Fig. 28. Cracked (Th,U)C kernel. ~ 97

l 1 90E909 N/C p gi ? g,,' W. ~ ju e. w.;p;e. c : y. ~a n. s j.). h4 [ V;s...e m.- zt., a Qs.b -W . sy -

s&w K

fy .k

"...?g i'

,* %.y.c :n\\.. y;f ' e a r m p( ++.r=g il g /sk.: W:-v. p.3-O yn

.e 8

e ;-. '/}..l,q'.s, m y..p ' g rf;,; *[f. pg s.jf

• J;. ~. Q. g.,1 u

'n. 4.:7. :. y' y[;- q ? !.. 4,;q.~.,.., D;r +p$q/ p[i.,, : ) . 2 M M.Q. 'g.. ,. ~., . v.c. h -t '. i. .. s':9; qt.-Q9- .:e e g r.. W,.;- . d.y g.-' G'. ; . g.. .r-t, qd 03lrl-,yG [g gi ? w, ' ~ W. ./g; e

G;T,

,.e.

,m,,. :

,ve.. %ge g .\\... a w g. m ,.q p. ,r .x.y . Y;. . f fk k

• s ~; 2, 7 ' j' l.Y l, ng

~ 'I tr * - ~, y %.*9&. r ".p s. L. J. Q.% ' L. Q~ e:>u n ' wg t. % e.'

4. w, 4 v,

' T. ',. c. ,s v ,,C 70 um (b) (,) ., 6:Jir. kb N Q p a y? i5 %E v 'S

49 y

/ Q. y$. / 0.'@..N W . p u., y I Y [I J . ~' [4 ' [ 'i N

• fj '=.

1 = a.:.,. ~ K A (c) Fig. 29. Two (Th,U)C fuel kernels exhibiting localized swollen areas. (a,c)arebhight field illuminated and (b) is under polarized light. ??

908909 N/C N '\\ ,3, z ~1, b ~ c. !i$ ),) 'l l 4 h 'r f '- l $ h$nd!" L)l 1, V % 03 i,T?-Q ' i$ ?$ w s g,J}$' d'k .'6$sY 1: b l 11 1 *W*' gj'A ib %g.3, . ~r i I 5 --'t4 -.- ~ .e q m. 'f 0 :, Fig. 30. Typical buffer debonding in the fissile (a) and fertile (b) particles. 99

908909 N/C l i l l 'h -.m.3, ~ .z n 9.2.~ 5 :.::;. l'. . l y ,j C' " i 7:;.( ?%: ~

g lp~, 5

h). 7h

I i .i, w( t 4 3, w. h *, ; _ .,ff ; e f ,[ ,;i' $ a, ~ M-g c' g .z@7,,y v.'- g- .,,' D7 g gaf I ~ ,.y ~1 ,. ~ .y a. S f ey ,A ')y&Ql*i:. u ET' 100Jtm 1 Fig. 31. Buffer cracking in the fertile particle. i 100

908909 N/C ,k 's 's-- g ['4 * ~ {f_.., - Q ,;{ hr e h 's

s..,

g C, :# 7 :;;. & ~ ~j v. ~ N v .%.v A [ .\\(> f f.~....,,.-. g. s s .V ~ ~ ,s-g' .a ~ '..e.' eR s n ( I: 4 3 s. .h..,5 g,, l I 7 8 s M l - I f',. i. j r .j ' i _,? r \\* o .{ 'y. / e s _e p. 's;,. ~ ;;.... y

• _ _. /'

.,,._.~

. -4

.l.,. ) ;,Ng.. -.f:j, },

y,,,,g

,s-s e N ,* i 7 ff D W a 'N O~ ~ ti; 70P Fig. 32. Debonding (a) of IPyC and failure (b) of the IPyC and l' sic coatings. 101

-r-w 908909 N/C 1 =M i pfh'-' .4,- . 9,$ ' z ' Ff.I . ' ^

7

-N' Gy 3 ; '-

;;9, i '*

.,*.

r j%.... ,. p*y L ._; w...~4. ,b. 1 /., v 4 .g 3., M*9' ..? n 4 ~,.s, r, ' 55'.$. jy .T 3. f/. Sy. 'M k i . ' ',= ', [l ' l. . j.d.f s- . g-s t ? . w

l ye

. s < m, 3 .?.: +,. y }p /t "y ty - a . + .,y z; 2.. . f;,

3 i i

+ t .+ _. I '3 ,; f g ). j $;.b. ,..,. f *. jh?N ' ?Nr. p-j.? E ? A (#C.'J.Q, F. d ' #_,..._,, # w __. -.c g .0,,.- i M' a, p M ~. )W, O())Y Fig. 33. Failure of the IPyC and sic coatings resulting from densification of the buffer. (See also Fig. 29). l'J 2 ~

908909 N/C l l w((+,'? h. ' a s? g m gd w%. -,W a 2\\ P r - tC - ~ ' t.:,,, 3 "(g g%- \\.k kg \\. -.<pd ^' ,{ i s , Y.yt te M-4 *- Yg; _\\' ~

1. (%[e.p3

.g w. .s fh ,t a As .12 . Q: +@N [y, *.sye<Y*;.'s p% 7,; [' i h,;;r m 3 $ p1, i /.

• • v -

>$U ./ 3 l 12 ? e. . - e... - p .p

• '- > * [

. 45& ,*} ,,f f

• -?

'f f l' .f T =1.5 ".yV ~ l-Q mia;.fd&p.v a w_,, t ...,. = r '.go % mu%rCi p* ' - p%

c.e.

Am...g u,.v/ Lvh3 - i .ss a _n (3) (b\\ ~ .30 tim' yy' \\ Fig. 34. Typical lenticular flaws in the Sic coating of a fertile (a) i and fissile (b) particle. s 103

908909 N/C i i L. ~'$$s h b,d/. .i); 'h'7\\], :~, w r w= -:Y: / ~~. %.W ~- I .. W" .:;jiv}h';51IU7[;UV :. [ ' # $i ' '" ' ' ' s ' b ; -, '- i a*- 3 ..s s. ' 'Q; h- ~,/ W. 7l{ :s ' ~: x , % :,Q ~ q. u ,. ~. %M 1y i:s, s. v. ;; s, e.s. - M. ,l [* ,.v_ r l- ~ 18 1 3 / i w ~.9 i A0' ? t. 'e s a ,c g,,2 ^ fr, 9 't! <9 .d

.l

, h ;. k,3 ,,b \\ ',u, 't ~ \\ n ;, ~' pf( w. o r M., h r,qs,#,7

• er,d7.g'ifN Y

1. ^"

l '= { 5 L, ,k]. " $7[ ' Q(*Q.. ',"..0.,~ ;?_.. ;..h n.. ' f ,,.5gf.?*'~ W kNf.k W f' f a

• *-Y Q

'r;... :,$ ..u i Fig. 35. Fissile particles with heavy metal dispersion showing chemical degradation of the IPyC and sic coatings. O e 104

908909 N/C Ti

x-

,c ,I d: 'kfhj{ b ~ -:ji1 .x;; 17 i J' ,,./ l ? t E if]a } t i s (c) (d)' ~

O 5

22. -

l Fig. 36. Top monitors from holes 67 (a,b) and 18 (c d) show cracking. l The cap was cut in the monitor from hole 18, but the l monitoring devices were useable. I 105 g s

908909 N/C l s ~m y ,% g 7, .fo n?f:. '05j, *' 7 7_, t \\

u.,

y, V

• . ~,

- f.-4' y 3,: [ ((', ' .';,1 \\ ~ &,. ' .,i,

i qp y

, ~,. ',%Q.' -y

• ~

j .., o 3 i \\ l 1 /h's y%a, 1 ,,a: , Jr I- )%;g4 'l l. *? ~V ?;, \\ "g*~. ~ ** y L.. . l* >l,% - .... - - w% ?Q ' ,. l, 5'$ ',' ? ',... : .. t v;.pYc%u. g, en,..(%; y : .w .-.z w s -9^ .h, '; ;- _* * *p$,, ',::;tk _ ',o 'Q., ;,(( i * ^ , A', ((5;*;h t

• +

Q?:.M ., fw: ' . g.,,, 3y _ $_.~.:;* ,,. :m Fig. 37. Top monitor from hole 307 showing cracking. This monitor was located under a dowel. 106 -f"WW'WM*W-wMvww-m a m ---~~-w'~-- -v v +-------"m

908909 N/C l l j*: i< j;.v. / [.f., _ l g i 4 f J e / I f .,ft ?, . 14 Fig. 38. Top monitor of hole 86 (4 monitor stack) showing cracking, i I 107 l i l l

_. ~ _ ___- 908909 N/C 1 I ] \\ ^Y.-

• ?,

= I i s. i i i t l I l l l t 1 J e t l s, s. s 4 L t - -l. ';. ~, t.ij[ *;$ O Fig. 39. Cracking in second monitor from top of hole 248. 108 i

908909 N/C l l I l, I I e i l y, o j \\ 1 i 4 i 1 i j l 1 a i i Fig. 40. Cracking in third monitor from top of hole 248. 109

908909 N/C i 1 e 1 i l l l I i c '~ I ,3s r l q ' y, ~ . _g ,. y w -- 5-ip QlN ?.. Y'

• r\\

gs ?<.,x* r jL4h'4% 'y;<g

• J-**,,,> ^ e g us m..

p i ,g ~n K-gf, t.,

• * :.> x;;'%(

' 6 '. J

• 3

'4. p +7 9 ** ~ ') * $. a* . st. - 's, 1 e wJ =., sA,. . ):.ga*27W.h,. -,k e., ";-. p. > ... y u.4,3 6 yl. ? q.ygr. s. . yp %.'a % W..,,, y %e;.- <.y;& 'M 9-u e

. ~d t ',.. T p :' z.

4 V > "e l 4 t,t p.,. h ^ *U i, gi$((%, @{ .,6j- ,;j 3 Ar '*45 . ; i.fi{$/i'

• m,w..:h;

.M.jf['/A$[[ v-a#,k e 1 l.N5f l 8 1 l Fig. 41. Cracking in third monitor from top of hole 86. 1 110 1

908909 N/C From monitor

1. 1 of hole 248

..t;

• A -

~ '

4

.~ g'. c l 4 h l (a) ,) 1.) i 's ' g 3h )' f l lg .,, L ' 2d[' ~ l hyy h )'? k y y$* 4' ,;;s,, (yk + ha 2 ]s,1. E* ,' ' 7, i lh Y i. N.. p 7., ) yy -s .. f e

,';,'l. "

,u s :i e >.;- yt/?t n,.. b) (t) Fig. 42. Metallographic mount (a) shows the unirradiated and in-situ Nb-1% Zr tubes; (b) and (c) show an enlarged section of each, respectively. Note the swelling in the irradiated in-situ tube section (c). All

908909 N/C 1 'T :?Qf@hyh e. 'ty 4 M: :.;" ' L..y' 3 9 h u p g:y *'. y ~.'.,, & yfg ~ (yf,sG: . <?,. v. '~%= g 'R; } :o s 9 r 2 },g l~ gf ,;a :. l ~$f' A. ..w - w (, ~.h( -' h. . ~. ,lh f g ^ E ~ w; ;;_ '

• Q.,

4( q.- ph gi AV/ '1y 1i...i .%,ff~ r. c. \\ H a.g:;^yW c. n. + e' {b 8 h5l } f,,, ? p?S:5, csk'. ! }4

s@cDg%:f G. f

..? y 2.j; 2 f 6 6 yt pi. 5., 0. gi? a L= f k_ - ,z .,,,y. N W: ' Fn 0 ".7d1i,f i }j '~g l grf, r [.; YQ ~:g. 7.. g.v ra,:.,,d p '5,i.(f t is. ya, .. ~ 'y l.ty $,s M. ' p p b'. .,G ~ f,. ' i., jypQ ' /., (e. g y.

",, ?

.u.- f, a,h.- i ,hfi Yi.

L

%g,r.:yw

h5;gy;w.

' g' ' w# ' ' t Y Q n, 1 c , 4[Q[:,.,, [h5 _ k N . N{.}, L.* sh p,r"....g }{'* {,.j. h.),( ~ ~ ~ .,.5 {.,/ ", % c. N R 9 fj f. e p ? l,. { '

v:l*. y ',

, ;1 v,.>;, m,. y(p -r.6 -^ c,. ..c,- 1es

• ,;r.

m :- l -z. t' 4.,. e.., ec,,j .~.,% 4,; *fg 14, - sy .. ! 'T 3 l., g '.. - i.., 4 .~- j, ,k",, I )- Y M s. _,,y. (- g,. .w. - < ) J.*

II 1.('

^ q lN l e l,.) .,.l< % ' + 2. 9, a, %'y J a'.;-~ T J g ^.'(/ ^ v- . - t.. .... c.1. y:.... - v..se . A :.. .m l Ah, rwa e.? '. w '. s Fig. 43. Unirradiated (a) and irradiated in-situ (b) niobi'in alloy tubes from monitor #1 of hole 248. 112

908909 N/C i Arial Cores 2 4 6 8 Extra-v v v v v v O_ CD C C O \\ .i .i i ,I l l' l 1i i i I i ,I 6 + i I-il. l', i i l ll ll 'l l l. l i i u l l .i 1 I n g

J l

I i w a , j m il I 4 l l. 3 e f i. j l n !l g, i N m i i l .I.. L.,. e s a .l 0 l Cr y e ct a 1 4 5 15 13 11 Buttons 4 s J Fig. 44. Location of specimen cores in Face A i l 113 ~. _. - _,...,

908909 N/C Axial Cores Extra Extra / roken B 8 6 4 2 = l l l l v v v =.: - a ~. I i ii a 'l o m 1 i I,' r,

t

_.-_._.____._a i,, 2 i p .I o t l' a 5 l l l 7 ._.__.__l I e i i. i m Extra I l l t. o i u 1 o 11 >. _i l II l o (5 E, xtra _J = s y 7 I a ._.__a m g 2 5 g o, j D ..........._.] 1 i 15 13 11 Buttons. e Fig. 45. Location of specimen cores in Face B P: 'i 114

908909 N/C Axial Cores 2 4.~ 6 8 . Extra G, vCCOO \\ v v v v y, Ii il i 0 l l l lt i, [ II '.l lt I I i r I l ll ll ,l l'------._---__. J. I; l !'l i, u i \\ l g I l .,l l g l I I u s .l m 1 i l l-l- l._ _ _ _. _. l. ~ g i i ! 'i 1 y m 1 I e '~ J %..) L...' L... > .... ) g en n M e et rA Ma 15 13 11 Buttons t Fig. 46. Location of specimen cores in Face E l I 115 _m--.- ,_-y_-y_r_,-.,-_.--%..._-._m,.-, -.f-

908909 N/C Azial Cores 2 4 6 8 Extra v v v v v ._ v

• wOOOO i i il i

l t i l'i Il i i j i y l l; j I i. 3 l l .1 v !ll l' 4 i l g r : ! li l ', [ u s i l*l Il g a l, j j i l I m l t,..a I....e

t..,

1.... ). _ _ _ _ _ _. _. - -. -. _ _ - -

g = M e er m M B 15 13 11 Buttons e Fig. 47. Location of specimen cores in Face F 116

908909 N/C Azial Cores 2 4 6 8 Extra ~ v v v v v G. vO O c~"') O \\ l. i! ll l, i l i .i -i ti i

ll

,j j l ,i .i v i i i g l l .I n m l u s s, l a i I, j i.j g i s l...a ( _.i L.,_ $ l....) 8 'd o o tra M M e e Mp 15 13 11 Buttons Fig. 47. Location of specimen cores in Face F 116

908909 N/C _.__._.L.__._ ._.__t.__ ___. _..I,_. _........ _.. .t_ .. ~ ..I.__, .g.._..._.._...,_.._.m.._.__,._._..__m.__._.._. .._7__..... .. g.... . a. ; L 1 : _ _. __ _ }i. __.-. :.: z.. _~.-_ ;rJ.__ ___-_g_.__.......... '. _._.. ;:.. _.

..J. t.-..:. A :. _ ;:..

. 1. _,.. T. _.:... _. ' ..t-_ .g _ .._g.o_..._.._m__ _. _.. A _y... g. g. g _.... __ _.. -. .. -J

• • "" 4 JF

@ bl. ..[._ _...__'.*?*i'".5. &...T.;M _ _... _.,,..M.. _' a ~. <. . ?'"I"* _~ __ _ d. l_'__ g _... !'~_ _. .~. I I 4. 3 - _ _ _. _..'_"":._,"'"1 s.f._..__._.'_.L.. i

7. s _...._

..... --_4_.. ._._(___.. . g g _y ,./.~..'_""~_T__;.,e,_........_. . _ +... V ./..._... _...,,... _._ i.__ ___;4._.. .. i. td...... ... e a. 6.,...-, _.... +. 4...... .. J. .._.,s... _._f.._....__,_...._.l e ... o._.. ...r_ . _,.._.... r,. _. -. ..+__~. o y - 7 .g......... D_ _ _4, d. _C. 4, f_^ j b-9_ . +. ~ _ -. D..'". N e. _:,. ..= m.. d... l. f. _..~ :,. ...:/. .I..i,l,C_;' O. .; J Z- -~T i ~~_ ~;*_~-

• C,' ' ~..

C. :C...]+C. _ W y!.. ~

L '. ~.-

_.. +. -. ,_4_ ._.g m..-..,. ...t.~. . _.e... -.s .. ~. - ~.,. g y .a+_.. .y. g --.. .a 1, _.,p g... .. J. l.- _. p.. l.......+..; ....+,..

ni in: (c..1 -_.

~. g, _ _... s. _.+. ..(..,.,.,,..".. b.. 7.-.mw%.ci ,,4 n Wm :.ni h:r m +1 ~.i4t mim : m (.. _ _.. - .s . ~... -..p.6.. ........s .. +. . --.y 4 .r ......r-**-. rf.. ../-. .:tm. xn ._._..s.u_..-... _... ....n.... -..,... .. + _.. .._o_ ___7'_. _ ..t_.. ..~1__.. .w . _ + _....I,~_. t_..,.. _. u~ . + _. _ a_.. ~.r ..., _....1_..._..._4__. _.4-__... .._.p.__... _... -...i.... .._.4_....... __.I._.. .r._ _o,_._. _. t. - g.. w.-.... ._.i.. .t_.._....,.._..

1... _.... -

._.._..J._....._..r. .. _. + _. _. ..r.._. s..._.......... _. +. ._+ ... ~ . + -. ..+. ..i.._. ... _.............._[.._ ._4.... ..... _ ~. _ . +.. _ ...+. _ ~. _. . _. _ ~.. + . _. + _.. + .[ .. +. ~.. ... + _... t'... __... .v_ + ..9 ... _... _ + +.. _.. ..... _ _.........t_...... ..r_.. .....I.-...._&... 1. ___4._. n-i- O ...5... 4,. . ~.... 1.. ...l.._...-...... ..... +... ..4 ,...+... .. _....1_.... ....r._.- ...o -..4..~ _...u. t.... .,s... N .. +.. ..w._......t..__. _....r-.-.. _...... _. y --.4.._ .._f._.. . _ +. _.... _ _.. _ v. -+-i.-~. .4.. - - + - + ... +. - .. ~... .t---*

• -+ - -

+--+*- .+ T*~ p@ * .i_--- 4 L...,. .4. .t. ..;._...... L.. - L. ..v i .f ... -.. + _.. ...}._. _... _.. w .[.. ...{_... ...,_.,. _....4_+ _ _.. .... _..t. . ~_ L.... ~..! . ~. -. ...~4.... ._..o.

• ~*.,...***

- -.. - +. +.- +. +. ... ~. - ~. + +. - ' ' ' *. * . * ". - - + ~. '. ..~_.*e_-.... +.. -... _ - -. - +... r-

• +-*&

-. +. -..*~.*W.*.**. '. ~ -. " * * + + -. -+ ..++.4 ..+.+4'..-..* +* .. -... +.. *. 4.*. ^ . + + - +... " - ** .. _., - - - + ...[.<._..- 6 4 -.++...+... .+.4.-. -~...#.._.-_. _ +.. , ~ _ ...-+ - 6- .-~ +.+.

• 4,.

h..++. + +&.+ -.+. m. + .._..v+.., ..o,-. 4. ._e .4...t... .o.. .. + = e.

p.... ~

n..+. ......+4.,... o.n...s.-..~, +.. n ..s. e. . -. +. a.-. .e. ._ + o_... ..I... I.. ..4...-. + ...o. 4- .. + +.. +. .... 9. ...i. ..... +. -..,. +.., .-.~.p.-... tg .f.*. .~,*_. e... .t~+ ...A.-..-~.++ep.. ....m.-+. +_.&-+---. -+&...._ _-..4...._-. t-*+-

• • t***. ~.,. -

4..., -. - 6.--

-- t... ..4 ..m. .. + + + + - - * + - + . - + ~ + - -

• t
• ..-4

.*~ +++++ +. +++4.-+.+p..---'.-.*+..h...+~< f &++.. ...*4 ~*4.,.

• .. _.. ~.. -..... - +. + _.. - +.

- r. ...r._. 4._.. . s.. .._.4.. 6 o* _......4._- s h.* - E......*.... - - - ~. ~ '. - ' '. * -.****'*-+*..A-**..* - - ~ ~.. + ' +.. - -.. - ...+4..*.-..._.'*.k*---.' M** p* *

• a++--,,

I. - + - * '.,. " + - + * * ". ' * '. * * * * '. ' - + +++ ** L.. '_.m...a-- .**.['. ' - ' '. *- -.. - + + ".

• .i

). +. w. s m .4 m.. .g h,,.. , V. .t... .. _+. (s. ....t.-.- .. s... 4_. ....o... ..6....- .. +... _ t...- .t.. -... _ ~.. g-.... ,&4 .t.. .-..t__.... y _. . _._..e.__.... ._... _.. _..._....i. ..[.._....... '. _. . _...... -.. _,.......,t.. ... _ + _.. _.... _.. +_.._... ..+... ..~t_._ .. ~.. _. _. .+ .t Q..,_~ ._.i__.t..._... --t.._ ...p ._t _,.. _ .t. .[ .t.._....J.._,........ {_... . _...... _.....p... ._.1... ....-..p,.._. .. 4.._ .s. .A_ ...t... l..... ...... _...... 4......._..g:... r:.. _ .g_.. - '.._,.. 4 .._.r.....t. ig M p ;.g;--....r r t m ~;.irr 4

1

. ;n*T p w g..... _....... _._1_.__. nn : 1 - + .._...a .._.-.c--....,. -... .. t,. r . t._,. i .... -t.......t.._. .y. ..4.._._. d,.. 1, ............_L_..._ _.. .... u.. . +. -. y. ~. -. _..-_..-l_.._. i i_.. _...w........... _. . i ........._.+._. ......_..._.. r. _ +.. .. A. ~. _.....-:.. 3 a f.

r...

3$ 1,

c. r :. 3D.d....

. b;- .C..I., -.

• N.r..C:/l_-.Zf. ?..fq,.

. !.O!C

!I

1. ;

N* g.' h' t.Q.. : . _ : '.;. '. _, J. '. '.c#. :. t : 7 M. O+. _. ,. ; M. T, C...,.. -/...,t.r.,. /_. U t,..! .t g. e ..f.. _... 1 --_ .n e ,.s. gn..:Q {,,j -... s. Q ,.a. p l -f . s. .. a E. p i / ,/..- M: !- }E 1:~, + .. f.,. g.t, C... 1. p* n f:: arm :. ..C. :;*

GC m irn~:( ;!M n J, W nt:

t- ".. " Tum.' f g .. y N,.4 ..O_ .. e._.,... i. 2..._...,.11_.._.t#.__....g.:,. .w..,. _.. p. v., ._..... v, . _. _. f... g... g ,~4. ;5._.~ s_ s....... _...t... --_J.._... . + ...,,J. ... -... y.. -.. y g _. _.. p. .r_ .,,, + ..p. gg 4. 6 ... _ _.~-.m. p. _7 j.. g g.. ,-+.p.. y.. e.. ...f_ .--e ._.. j..

)

..,.. -. -..... t..... -. ! _ - .... _.. cfT..l ..i... +.4m....._..+.5.~.,r._._.. ._.I.. .-.-..t ..t _... ...... e e.- j

9..

..g _.j. ..~ .}..-. . -...4 ........6.,-... 6..- .e 4 4..-. i ..(.... .l.. '**+.4-++ 6 M -*M 6 e ,.i..-.. + .4... +6.-.*+. 4. 4 .s .4-. 6 8. k. . } --+,

3...-. - -

g '"8..., -..4.+ .-4. --t. .a e. - + .4 .-.e .- 4 .I_ -- Q g. a _ ~ ...t._.-.. ...1.---- - --t,. ._._.t_....-.,. _.,... .. t _~. _.. -,.... y .b... . -. - - +.. - - - ' _ -. - *, ~. ~ - ' -...t.-- ' -. _ - - +. * ~..... .. - - +... .g. .,N ..,o &....,_..;. .4 i.... -.... ~ ....i.~. .....v .-....-,6. ..t _.+.... 6. . -.~f+.-. ..uo.... -.+,.6+ 4, .9 .e_.- ..6..- +*4*- p. .++... 4.... .. +.. _.. -.. 6.. 4 .~. e.+. .. ~. - + g .4.-....,.... 6 ..-.u. ,.....4.... +6.... .4.4..... .6- .(..- 6 -4,.......4, ..6e.% 4 ~. .....g. ,p . -.... +... +. * .. +. ...., ~ ..4.......n4.....,.4._. L. -4...~. .....y.. .,a.. .,,4 .. e_ I s 4 ++.. _6- +m. ..(... 4.- . +.. .1 4 a. ...+.. .l.-. 6 ...,.,....u .!_ + 4 5 . g p ..... + + +.. ,u _. t_. g 4.. t. 4 ++ ..... ~.. .t.. _ g ._......e.. .1..

v..

. +.. l. .j.... .........J i A '..i. ~nt.... a...+.x.: +A.... .. ;. n.T

.L; m...; m..;.

.. --.fe.... .1,. a - ... +.. _. .1..... _... . l..-..s.... l,.. _.- /W.t.. O F ' : :. Th,,utd __. . E:.L t:. gB- : t. u:

~t 1.

- :;x - =: x :- i !...:= - d ::_. - l 1- +- i Figure 48. Tensile strength of H-451 graphite from fuel test element FTE-2 for different faces of the block 117

908909 N/C j_..

g. ~. f. _.

' _....- f c ._ jn g_ j-]huj.T

1.,

_ '_{ ~ z[ _.-. j . 2 ;_

f.. __ j

f. '

u-] - . :i _ ;:n _.. ; m r C.

n;m.

_..c

__ +

__.. : 1 t.

!:.. :t: *

!x..._:

..:n :r.. --

n n=

xr - }:=.

. __ _. : n_ .1 : = = : _= :=*=

:

x:. _

• x.

.:n _.L__. -* = + + 7 ..:. :{:7_; ; _.,_.

2. L

_..o

__7,

..i .. =.-. :_n_ x. x.. x t.:r__c_r_ : L_. r.._c.. t. u_r_-. m..L. u* r._x_.- r : =_ _. c_. _.

't.

!~m:

=._ : :_.x U n

. u t..:

_ t_u.. _ i_. _n t. J u n.. '-~~ q h. s. .In._. _..I.... n-

J..n ;. :i.. :

I-.

.... _ _.d r - - ~ c-....... .I.

I:

x:: r I:..

b . t _. n.-_r__. t _r_. n_n_., .! : x : _ * ..}.._

n. :r ;: /M. W q {r.:.1. _.. __.:.r_ _: t n

-... ". t :. :. ;n._n ._ t.. ..t..

li~jj[ ifji

~i(( hi[:h ~-d;[.i- _'{ Tj-'f: - fiij'{ j

H:-

~iii ,j [ i

1.

j:.

.x

m:.:2 2 n:r.. L: z: tr :=

. r=1 _ :./ -

! m.

_u.

. : =. m!:n: rz:nn T xt. - -inz.

nn!"1 .r::. 1. S ix!!!5.miir: =!7.. _ $i25l35 :55$Ui.f~-ifE: Ei.is.fhif55 55t 55EIi5 -i if ~ _...7._. x:!~.. =k mi= 9-

-- =:::.n n.. '.1 ri:.:_ x~==

n_.:nrJ=t=.= trx :=;= rnirn.=:: :..du....: .L

..gn"

-~-t--- =t=

n-- = :=-==:nn m t zn =trn

= trr '=*r: 'rn!"- r:t - - - + _. _:# d:: . -_n jn n - nt:~~. N 6' :.

;=. :=:

nn,. min. n :i:.

.:tr - n u t=

g.....g.j ' '.;- f'. 4 c.; I

x :'= =tm cntn _

• -1.__

n'. ' a r -*-a n :!=. CI--- _. _. nr .i.. ..... j _ _..a. d. _......... 4......Jl. %. .. gg ... = - w,__. _._ ' _ ~, w w w,w m n.m. c m m m.. - -- m,w-

v. %n o

.,s a e. >y; _( .n N - a 3

n.t:.. _... :... _

4 nr. 7......[____.= =.t..=. _=_?.-..=_..tr. _a-.. -.. V[:./ : _. - 17 2

=.

J. ' =2 2 L._..:; r _.=.-. :. =-x ; m.. ~x.in_n ~ ::: n:

}:

cir- ..:t m =dnr un;=

;

:cr cr+

.m: _ c ::: T -_ 1

t:

. - ntxr 7 --: x na t:-~ -t=

"xt=

=tnrE-*

3:!n-. .t.

{

1:._. :=.

. n ::. : J =; :.. - nt= :nu;=..mt= crtur ~6: _u {. : ...:!:. c {: c. i._... " - - - t:2: Lux;nn :nnt= '= tun :=tur nn~ -. = ; nr LA N u __a_ m-L:.r . ng; 7 g:n1.y..; _ q.ix_::=.. m.;;rn r_n.; r r_n.. t. r. :=_. ;urr..r ;r n__ : =-.. t=..n

=7.. r_=...

. =._.. r. u a ()::;r.

j-

l:

. : {n. -

7..:. :....

g.n_. x.r.. t r. rr. ;. y=.-

..r :. r- _ _: t : .y l _I ] ifir C -- - !' - Clifin: liCtih =55-3= ".i - C:{:. ).;: .;_ :l~ 'l _.4:x.

! = :

1-

= t

J.U:

1) :

.. :::... p. t . :t-m'-- "_.:: = .z i - ~. .g ,=.:=..=.;=. t. ::t. -. L. i c ~ _ 1'. . t. : ~t. _. A.

l:

g.. i *

.A' .J,:.. G.. ...{. ...@ :. : n.. =.y.,g ;. . g.1 ir . g. - ?d,. !. .t --- r-

t :..n J :+ :.n

..:t: .I. . t.. .t._ f 'i 5.. . I. _..' ~..~ ! :...- .j: i f.i . f_ :+. .. _._i}

j :.

'f! .+ .y z. f, if .h I - i- ~!- ' Zhz - --- i - ! d: I s

h

. i.l I ' t $:4.1 TR .M 5 W O G =H.i= =:"! -==i=- =: ! - F 1 .i p' :. hi ..'m. f. ~'t'***

• *
• t" :

P* ?;. n....... ......-....................1, i, y I + ~ii?, wim ~ ~ N g'.; - V At.U E{_ .g ja 't -- m %% %-sw !**:--t N !": q m:: n.C. y_ / ~*-* :

• 3 y&:J~

~;,{: .p' :, 'T y:._ ;grJ"*" 7 -f ,3 .e,om. m.w.m r :f1 ar o. g .-q.Or/' r

t

-6 ' N' I .p i 'l + . _.,._. 2.._i ] . 1._ U!..._.. i t i. 95 't i I 56T I j: g. _.7 _ ;.._.._4_.-_.-.7.-_ t .t., .i. l. .l- .b -q _g.. r 1 '{.

t.

f'

:

t:

. *{... . +.. .....t._..,...;!: _.. l v. ut_:. _.. .l .t. t. J.... .t_.- i p n

I...

+ .I.. .{. .i ( ..l.

f r:.

l T _. a.7,.... . n. _g_....:. _.. __..t__ y .l. 1 .j. l-t-

t:

't:

t:

't: ? l t

0., -

3:.:.l:.

-g:..:.!._:

l... tm

A.

t. _g : ....1 t ~... .... m 1 .._.F. ME ! OFi 2U%. Efi.MWr !!E m. ti: 7 a. 1 ._ _.. t: .- ~. . m. - j T _a Figure 49 Young's Modulus of F-451 graphite from fuel test element FTE-2 for different faces of the block 118

i l 908909 N/C l l .._. _.... _ _.. _...i._ _.+.. _ _ . 1 _ _. _...._...,..___~._._.L....._._..___.. _..+_. .. _,. _. _ _.. _. _,.. _._..p._ . _.... _.._r.__ . +.. _. _ p ,__.p.._. .p._.. ~ _. .. +. _ -.~.,_ _ .-. _ + .w.

• • _.. i

.J. j __e_ .. + _. . i ..__.r._. ...s. 4..__.__.. ...., _..... _.__L-.,....+._,_. _ _ _ .... _ _w. + _- ..._.-. w _.__f__.__. ...{._.o. .._r_..l...___.,..._ + _. -.. m__. _. _--- .____._.._,l._._._.. _..g._._d(._ _. __.r_ ....._....._.. _ ~._..,. _._.__.... +... _u__ ,. _ + _ ..4 _.... _. _._4_...._.J,_.___.._.. ____.._.. _....__e.__. ... _ +. -_%......_c._.--.. - _ _.. __v...l'.--... _ _ _ _, _ _..__.4._. _ v _ -,. ;._ __. ..-.2._ .. ____y__.. ._.7,.-__ _...4 ~.. _.p .a..___._. _ _ ~. _ _ .4 .. _. _ _... _.+ _.,... .__.o.+_. ._._.r_.._I..........,.s. .._4.. .._.I.__ ._p.__.. 4 _ ... _.. ~... .....,.._....._._{_...__..__l... .. _ _. + _. ..._p_..- _J_'~_.. _r .4 _ _. _ +. _. - _ _. _,..___1._.__[_p,... .. _. _. _.. _ _,. _. _._..._v;_.. . _.. +.. . _ + ~ .. _ _,, _. _..%..o.___, _...., _ .___+ _,.. ._. ~. _.., -. _.. _ r. .....I.._._.__.;_._. _. _.. _,...._.9_ ___.__4.._ _r___

p...

__-.4___..-.~.T_-._. _. _ +, _ ~.._ _. ... _..,... _. _._w._.4..___.. +__ ._m._..._..w.._ +. .__4._.... 4... .__.4..__._ +.__ .._... __. _.,. _ -... _ _, _ _ _..__1____. ___.1_____ +___ .4 . _ ~ _. -...+..__ ..s, . _.._.. - _ +_ _ ,.-_.n_... _-.+ . ~.. _. +. _ .4,.,.

e. 4

.. _.. +. ~. + .n ..+ _e_. .. _ _... _.. - + ~_.. _...._... _.,._~.T_.__.. _ + _... w__. ~.4 7__.. ..-.._.~._b__. _...,. ~.. _ +.. _. ~ _. __.._....__....._. _, _. ._..r-....a--_. ..... + __.._.e , _... +. _. _. + _.. n. .... s ..w_.._.4_._.. _ _. .r _ . e.. . +.. .._w_..._.r._._... _ _,,.. .9.. _4_._ .... _ -..,. + _..,. . +. _ - 5 __._. _ .._4._... _ -..,.,... _ __..... .g.. w . - -... ~. D . _ ;_~. +__..._l_._. .___1_., _.,. _. ._.m.._.. _ _ _ +.. _... ...-. g.. ...._.l.... -.._,. _.... _.. [..._,, .4.,_ . _..._p_. . ~_ ~ +. _.~..e f_-___..--.4 .. _. _, ~.. +. _. ..T n. .-__.r__.. _ _.-.n__._ g... _. +... - ._-a . ~.. _ ..-q-.. .-.4.. ..p.. ...4.__.... ._4.~.. 4. .. _...l.__..._..m.I....4.,...., _. _ _ _._ ._,r___, ..__4_....,..__._i_._.~~. . _ap _ .___ +.. .9 .+. .___ o _. ._r, . _ _ + ._,p_ .._. - +.. _ ._..s_... .o._ ._+ .. _. + _. +..

b..a. 4, t

...,. __. _. _ _.._.._._..J_4._.. _.e. +.... _.+.+. .. + -..._._._w 9.. o.... %.+ . _ _ +[...~ . o... _..y.-. ..n._. .+n_ _ + -.... ._.4.- ... _....f_.__._ .. ~ _.

9..s.mi

+.... . 9 ~. ...a .-.-r ..+ .. + _ )

_C $.** ~

~: :.. '. : b=* I v' i -=-=+ WN:O11W 'W "AC' 4i: .: W -'M : I'*! b -**. U^,* NM ._II* TL"*?[.'*.327 : +-L~. } Q.-Q- -d O --.~_.- .e 7_..--t."..a-+-'..'--s*pd._--. - -. + * - *.... -~*. - +-^- -_-~n---.'"__._-4' '. ~.4. _ ._.'_a 9....- y..+_.4--_,a.. -- - 45.-..+ ++

• f

_p n

• 7

.....,s-.-.. +. _. _... ...y.-......s .y. .. +. _ . _ ~.. + _ e. ._. z a. 4,_.-. ... _.y.-.- .+.-r.._.--34. 7 .4.. _. _... _..- r. ~.....,.;- m ...p +,

a..._./..

:::~ O,...J

._..,.-*.n.._.~. ..J- _ .. _ r.4_...g _. w f',.a_.. _.p. >.. _ i +. .s. _r o . g _ H_.. w._.. ._..e__.-. ,s .4..... . t f... .~ . m._ r_ e

• * * * ' " * 'i......

.4_._.. w- -. +. : Id C_. g_'.~._:g.. r 1-~ ~**M7

• J *M *eM:

q . MP J.. ~ ^ * * * -. ' M "_" .... _... _.. _ +. _ _. -, _... w_ _ +. . _ + _.. .+._s.,.. ... _...._.-n. ..._.7 .. _ __4 ._m.:__... _.+... _._a,.. 4 _Q_%_,_.. O__...,.d.-._- ,..; _... _... _. _..m..___._.__..#.__._ e.. 1 4__. ._.-q.__ + .-S ._..9 _ +. - ~. ._.y.____._; ~ .4_.,_._ ...#._...___l ... _....I _._.4,_._ _..,_... _. _, .1........ .__.e_- ....... -_.o_.... _, _ ~.. _...._..... _.4-. - _. !7 w ,J...u.o.._. .. _. +..,.......... _..-.... _..... .%...._4.....--p__. .... ~ -.. ..o.4.._ + ._.4..._. . ~. -.... ..... _. _.. ~. _.. ..o_...... -_ ,.~. _. ....+ ._4._._ ...1.._.. _ _,... __v.. .4. .~.,;....... _ u

e. _.

4 ...., _... _.,...L ~, _ _. ..o. .~..+.. , _. _..m_. .9 ...o_ .. _....... ~. .. + + . +. + .t .+.. .......... _ ~. ...... _ _._o.. ....... _...~4_.-_..-_. _.,.. _. .....,. ~ _ _.. _. _.,.....i.. ~_...*-I_...... _.. _ _+- .., _ +.. ~,. ~..... .... o-. _...__.p.. _. 4 . - { _..,.... .~....r.... _..i+... _ _ +.. _. . + +. _.. ...+.. .._.w.... .......-e...,. )...... ._._._-._4.._. ._.o... .~. _ .......o.,._. ._.s._.. o_ . ~. _ _ ~, ..4 .l -.t.. -...... _.....i ..+.._.l _e.. ... g.. (

1.. %r..

, o... n. + .. t.. ..T. 4_.s.. .._....w..-4._-. ..4._... . _....... _1_... _ ~ _,... _...#_... A _......- .o .- +._ _ . _ _ + _.. .._.$.._. _.,~.. P'-....,....-.......... ...i... ..I... .+ e_.. . _...,..... ~ _.. ... I _._ ..~. sr _.._. t.. u. ...s-. .I r v._. 5 _.. .............. +.. _... .+.. ...,. _.. _. p _. _..I.._.....p.._. . __. f r .....I....-. .o._.....

p. __.

..,..f... .[_._. .......t.-....... ... -9 ....o e .._...i.._. '. _...... _ _ j, .,.i,. ._..v. ...4.. ...._4..-. n .. i,. .. +. ...._..m....L.... _.. ..-..4........ m.......t.-. . o.. ..c . ~.. __.t*.*... . t _._. 3

• g w s.

...._.I._.._1...._.._...._...._. ...~. ........._...t_... _...,.... f! .. -................i.... ._ t.. _......... _. _. ...6.... ....r,... .... ~. _. ..r i .....' _ - r._. I.. ~. e..... n. , k..,. a. .... =, e Q -....,.........i. m.. 4... : -=J.y.f : m..... .. J..,

~,Z...

r.. ,a. ....-............-.... ~. .g............ ..,u... .. g., ... ~.., ... y: _.... _.- -. -. _ ( n-4_ p.... a..m _.9.. ......,f. .. ~.,. _..,.. _ ..._7 ..g. _g

6. ;:.3. M. :.n..ir_ _f. !:.T..n::!:#_,pE_

9,

t, :..

.L.,..-- . g. _ c)..A.... .m. i..n. n.h n. t +1 :1. uin. *. t: wi n %+: MI:r'r t: : Im .tM+ g... ..r._ g _. . p, A -. o e j .s., a.,...,... 1 ........... L..- .. _.. _.. 1 .t. n _4 . u... _. r,._.

o. ;..

s ~ a n 3 ..._.... _. p....._... . t....... .t. . t. -. i. pJ ...._...t._. _._...t_... _....r._. _ t...... .t. _. }.. q..... .+ y i . i. .. I.. 6 _ .t.. 4, - .... ~ . t. .1 . o... p. -..r.. _..t.. . L_.. t.. .i. ..4. ..$**n : ' * :~~- it:. ' I,. t n - 1 't: 1

t:

r +~ ...r..!~ .,7 .t... ....M.m....

4..

6 .. o. .e. ..,..e.- I .e. _..,,...u. 7 p .A_ c gp..c3, -.. L_.,Q.E. -L ..t:_:t. 1 _....e i.

h. r.

nz.:. . _.... r =.

r. c t

.t. ... t. i. _ _.... L. .m. i . m Figure 50. Tensile fracture strain of H-451 graphite from fuel test element FTE-2 for different faces of the block 119

908909 N/C ~.__.1 ._.._.e.._.... _._........ _.. _._...r._..___. .._..._,L._...._...__.. .( ...o__.. ...,r.. ..-..p_.r_.... _. _.._ r.._.. .....r.. ...o__.., 4.._.._.9. . + _, . _ _... _. _..._...._.i_.__.r._.._-4_._w t ._r_ __4_.__.._4._.. ...._o,._._..... ._.~._..]__,.....e. o.... I.__ _...4 ._+ _+- .__o.r_......_..4_._......r....._._w_... _.... +. .. + .. + 6.. ..,6- ..1 ...~ _- . __._r. _.y._.......r,._., .. ~. _ __.___r._._.... ..~.,.--~. _._.v.._ __.4_ .. _ _. _ _.. ____o..__.. . _. +.. {. .m... _~ .9. -... 4... _.__;__...._-.l_4_m....... .... _ + _...,. _ .I _._,.#- .._.-...-4 .._,l_..__.__.-..$._...._._.. _.i....._,. + _+

4. -.

. _.. _. _.... _. -. _...__..._{__._..... _....... .._.4...I.-_.._..,..._...._..._.____._-.4__ .__I...;._..__r,,._...._. _. '. _... _. _. _..4 ._.._.^1_.___,.. _.. . - g.. _ _ _. +.. ..._--+,._..

4....._.f.

-.....1'__.4_ _...e,_._...._4__.__._, _ +. _ g ,_.p__.._. r _.... _.... _. _ ....._v__... v.. +_ . _ _. _.._r_.. .... r...... _.. 4. --.. -... _ _.. ___e__. . _....._4__..._+ .o._-.. .._r. ..~.a._.._. r_-_.._. r. +. _.. _....,......_...,_...____.-.._.-,..-,..._.-....s..._.__+_._.___. _ _.. .._ ~.1 _._.... ....4._.. ._..s.__.__,._ _- ...o..__. _ _ +... _.. . _ + _ _.._._. ... _ +. _.,. .,. ~. .+ + . _+... ..e._.._..____v.- .,.._..._..i... _.. ~,._ _., . _ - _ _ + _.. .. __. _... +..... _...,.... .. ~, _ _. .t .~ o._ ..l_.._.,_._,. .... -. _. -.. -. _..+. .__.r... _. _. +... ..._J.. ....,o_.. ._4._.... _., _ -.. ...._. 4 ... +. _. .....e.._. ~g. A D . _. g.._ v _ _... _....,4,,_....___! ..;._.U.,.-_..._...._..._.,_ _.. +. ._._..,.__....._.4__.. _ _ _. ~ _...., _ _._.__. _.,.....r._.-._...__ _ _... _. .. _..... _.. + _ ..e__. _..... ..r_

4. _.

1_ 4.. _... _ _.,._..__.. _4__. .._.L_.. .g._.... _.._.. ..f _.._...__.r +.. 4 ._.o_. u.. ..__.L_..__ _. L_. ._.1__.. .4. m_ .._1...._. _... - _. _... _.. _. _. ... _..n. 6..._..._... ~.... _ _.. _,o _..._... _ 3. m __ ._._..+.. _ _, _ _._.4._._.._..__l gn..._... +. ~.-.o_... .9_..- .w .+. .n._. _ _. + _. _ _ +.. + . + _.. 4 .. _ ~ +. -_. .. +. _ w._. o_ . _ _. ~ _ I. ... _. _..._ _.._._..._.._a,._.. ._.4 ..t_he%__...._}.._...,._.. _ _.4_._.. ....,... _..._._4_.__4._ ....j. ...l... _ +....w_.., ~.___a... _4... _ _._. _.o ._w . _ T. _. _ _ _. _.+. O o. .~ ~. P% et o.. ...... _,...w.. p___ o_ o, . __ _.r .o_.... e ,7._. ..._+ - ,, 9 -._..o..._... ~... _ _._ ...o. ~ g 7., ,._..,_..g..,g. .. w.~i.' g .._..._...T__.4_~..._......[**.-, , _.,_.s.+.. s __ _a _, '. _4 a 4 I 4 ; i. ,.. + _ ..~ g. + [ .._"T- _..._4 .J.. 4 .._4. ~,.#..-... s-s. .._..f_. 4._' ._..,,p. vI o _ ~a.._ om_._ -&'._,4.. ,._e. p,s -_., _.,1 :. - .)._ } 4 -. r ,.f.

---

_p.a_..'.

., + _. _ ,e w. 4_, ..._.w ... _ _. p-..#.._- ...__4.. .. +.. ...,,.. _...m-u 9 m.-.....4 w a .p. o +_ (__ .A. %. m. .v. _ +- . +.. . _. w.. _ 5 a.._v. ~

4. -.

__.+.-._..~... _. .r._ + -. ~. -. +... .+ + .. _... _.. _. - ~. ,.y- ._.o._ . me.. ~ L._~....-4~....;4.... +. _.4-.._4- -4.-.. . _ + - -. t-~.. ~ ~+ - + - - ~ ~+_- -r-- --t- . +.. _. -. .d+..*..~l i t- '_-.-r.-~~..-..+e----_ .w. e ..r,_. .~... ....r... . _...,.. _.... -. + __- _. ..._.r_.... g -._w._. ._w. a +, C 4._._.4.... _ +.._. .-_.4~.,_4._.. .w ._o._- 4. 4..

---

o..

..y_._..,....+.. _. _+ ...4._. .. +.. l._.,. _.: _w-I .+ _. +-. L_o__ ...w_. w + ..g ' T.-._%,r.._....__ <- #_..._J.L_..... _o ~.. __-. . +,._. .m A....,_.-. _..._.-. +... ....,. _... +. _ +. _ _... _...... ~. ~...- ~ _. _. ~.. _ +.. _ _ ... o- % 4 _. :.__t-.. Z_.. +. _.. -.p .p..n .+.. -n. .. - + -. - - ._ +._ t ...w.... 4_. -o. ...... _..... _.,.. _..p._..... _ -. -. ..+.. e _... i_ ._.__n.._......_.... ... + _ + _ _ - ..q. l +.. _. _. _.. _... s.-.. _ ~ _ _ + -.. ... +. - - - + +-. 4. +.. - ~. s + N ._4__. _._. _._ _ _.. - _. _. - +. _ _ 5 .p_.. .w..+. +. ___. ... +.. _._.4.__. _+ __4_.. . _........... + _........,._..._.o.+._.... _ _ .~ 4... I _ + __. +. '_... _. + _.. _ +.... 9. .+.-4. (. s.- ..4.... _-_4.._... _7. _. .4_ [' A. ..._ $, ~_.... _ .- - l_... w_ 4 .._..r.... _.m. 4._. .. l _.. ~ .._.p_._._.,4.. . _. __.4._ ...p .. _. _.. -__4.___. _._,r_., 1 ._...o.__. .o_. ...o o s d 1.._ +........ _p. l + _. - + - +....... + ~_n.. T_ _. ..v.. +. _.. .... _~ 1 _+ .4u_... .l. -. .. +. (= _.. _~ .._ _~, 9.. p..p.. 4, -.

9. -

_,-._ + _ _. ....o f .. 9

1.,

=

..i_. .+. ..._.4.~_ ...i._... _ _.. + _ _. ..4 _._..,.._+_ .4_ .~~t--- ..-.-r._. .9,_... '. ~. _ - +. *

4. _

y, .. +. + y .t~-*'*' . f.m ..r....._. o__ _4 .__i_.. 4* .gw .-.g......._w.- _ _. _.. _. _....__ __. ... ; ___.4.__._ .q.... _ ~ _. ..4 =- A.,.. _.. ........4..... - _ 4_... 4_._.o._.__.;._. e ..o- .p-.. ... + t. ....9. .. _ +.. f, ; ~._._ + _...._4........ ~...4._.... _..... _. -...,q...... p __.. ... _.... + _.._...... 4.... .m......_... _,.... y = . _. ~.. _. _. _. o._._. _ - -,.. _._.~ ..v.... _..... ...4 + _ _ .q ..4 ..... ~ _.... .a .. _.,+ ...a_.....

• _.

e s.__ IO ._.... _ _.. ~....... _.. _ _.. r... ._.._.4.. ..m_ +. .,4._. ._.4_.. y +_ +_ _3 gj.....y.. _.1._..._..._.___.,... _. _..... _. _.... _...,. _. . + _ _., y y3 s ..._.4... _ _ _ _.-..r._.. g_ ...r.._.. .. _. +. _ .... _............~_ _. _.. +.. ._r__.... _. ._.w_.~... _ _... _ _ _...._4... _. _ _. +. .4.-.. gg.. _ . ~... ..._o... .r g g. j 4_.. ._ w.a . _... _.._m....... _e._...~.e... _. -... + _.... ._.4._. r___.. _.._.. _.. __.L _ .4_. g .._.._._..A...... . F. ~.. '~.. ~~"- ~ ~ ~ ' - - ' ~ - - r._, ._. '. " _ ' ' ' ' ~. _. _ ~.. ~.. ~ ._~.~r._. '. ~ . ~. ~ ~ _ - '^ O k. 1. g . _ r. _.._ _.. _ _ _, +. _.. _, -s . _+ _ _... .4 t_ r.. .....__..w_ p. yj W .. _ _.... _ _ _ _g_, .. __..L_.__ a _. . _ w g_ -_.r..e._...__.,__.g._...._._ ~. _. _.. .... _..__..r_ ..;+-....__.__.. _ _,g _ g. + + ..n p y m.. ~. e, n. y _..A_.. ,3 b, ' m m,..... g_= ..s _.__..,._,... f...,.u.q q.__ ._'g. _.y_ .-r. w W.*]r . br-w,..r - :t: T : -& w-7.,.. s ....... mmmhn h t.wr-e _ c r__r n!r r: ._..4 ...,.__ _. m.. _, n.. . _..._.i..p_4...__.. _ _.... _.... ... a... T.w ...r._... _...o.._4.. _..r......_.4.._... _ _..._4._. ..o.. ._._.{_.._ .v.__.. .w y. .y +. +_.. _r. .. _. - _ +... . _..m.. ._. p _.. p_._ i _p... .o__ .4_ _,r...... 4 + _._1._.__

4..

_.,.....__..+.., _I_ _.... _ +. _ _., ,4 . o_ -l.4._._..._. ..~q._._.. _... .i_. i

7. 17..

..p.... ...+. _,.~.. .6__... ..... _...,u..~.4.r... y__ ......4._. .,. -. }..... .. _.. + _.. _... _...f~_.. . _...r... ._._.w._. .e. .. 4 _ q _..

.+ r.

n-r n.

- : r...m_. ; Qp.:.g p...: p. () g

p.L. &..._ifi.4._1T--- ; - --

. __a._ cam...-.- =. 4.__ t_ .m. .__w+-- +--- .4 t ._.r.._ _... _ _,. _ _ .t. _._.p..._,...._._.._.. Figure 51. Thermal expansbity of H-451 graphite from fuel test element FTE-2 for different faces of the block. I 120 I

908909 N/C APPENDIX A

o...a. mm AR- 0542

/ CATechnologies 9 GA TECHNOLOGIES INC. P.O. 80X 85608 FUEL QUALITY CONTROL SAN DIEGO, CALIFORNIA 92138 ANALYTICAL REPORT (619)455 3000 54V/86 CHO.NO. J N @ r SAuetE J0. ( NOTE: NO MORE THAN TEN DATE / / P R OJ. N O. OO SAMPLES PER REQUEST SHEET. IDENTIFl. CATION MUST BE COMPLETE. ) M.T. N O. % EN R. REQUESTED BY d-O AUTHORIZED BY / ' ROOM NO.! AM EXT. MAT'L DESC IPTION o da r O l'Od I3 O om F T E -E Cw, uhi,,, 'a D S,yrhc, Rue l RECORDS WILL BE RETAINED FOR (OR ONE YEAR FROM THIS DATE & THEN DESTROYED) ANALYSIS REQUESTED 4 f M(>(m mom v nef3ndf"Ost onaku5rS u O n $ N e. O N F N eb fnrn OntI hk Dh a S,TN ho1 OYt~ CLY RO Y mn a n i -G;c a 4-,' o n. rA m k s k.a n w. o We I, ed ) v g ANALYTICAL RESULTS: W/ = AR % W2 = 2 / *Z a k k

1. J = s e 'z, d.s = 19 %

A d / 1 1 A-1 i

908909 N/C APPENDIX B o INTERNAL CORRESPONDENCE t GA 1076A PROJ: Hill [h% IN REPLY REFER TO: MAS: 47:DWH:36 FROM: D. W. TO: F. McCord DATE: June 10, 1986

SUBJECT:

Analysis of Fuel Test Element #2 Monitor Packages The monitor packages were received from the Hot Cell in lead casks. Inspection of each package upon removal from the cask generally revealed severe cracks in the outer graphite container. In one or t two cases large pieces of the container had broken away. Most of the Nb capsules containing the dosimetry wires had deteriorated to the point of losing their integrity and some had literally crumbled away. Nearly all of these capsules were extremely tight in the graphite container. In most cases the graphite container had to be crushed in order to remove these capsules and obtain the wires inside them. The wires were then placed in appropriately labled glass vials. The particles from each packag's were removed from their separate graphite holders and most of them placed in individual, labled, 2/5 dram polyethylene vials. When there were more particles than vials, the extras were all placed in a single 2/5 dram vial. The particles from each package were easily separated into fissile and fertile groups based on gross activity level. Six particles of each type with similar activity levels were selected for gamma ray spectra! analysis. The ratios of several fission products in each group of particles were checked for consistency to make sure the i particles were intact. The particles were then x-rayed to measure the diameter of the kernel and thus determine the initial heavy metal loading using the equation in Table 1. Since the edges of l the UCs kernels in the x-rays were not very distinct, the nominal ( diameter of these kernels was also used in the calculations to give a second point of refs.ancs. Tha Cs-137 activity from the gamma f ray spectrum for each particle was divided by the calculated initial loading of that particle to determine the DPM per l milligram. The ratio between the amount of Cs-137 remaining at the end of the irradiation and the amount of Cs-137 formed during the irradiation was determined by using the results of several calculations which l were made using a computer program called "FISSPROD". This program i calculates the theoretical radioactivity in DPM for a given fission product produced by irradiation of U-235 or Th. The fission product activity is based on its fission yield, half life, and j j depletion cross section, the reactor power history, the heavy metal nuclear reation rates, and the initial heavy metal loading. This pro 5 ram uses the Sateman equation to automatically correct for L B-1

- - = _ - - - - 908909 N/C (continue) APPENDIX B 4 o depletion of all the target and product atoms in all of the nuclear U reaction chains. The program did not predict all of the fission products accurately using the reaction rates provided, but the J reaction rates were varied to produce a close prediction of the Cs-137 and a prediction of twice as much Cs-137. The ratio of Cs-137 remaining to Cs-137 formed varied by less than 0.51 in these calculations which indicates that ratio is not significantly affected by the reaction rates. The FIMA (Fissions per Initial heavy Metal Aton) in Table 1 was then calculated from the average Cs-137 activity per millgram in each set of six particles using the equation in Table 1. This FIMA should not be confused with FIFA (Fissions per Initial Fissle Atom) or "Surnup" (depletion of U-235 or U) which can be calculated from the FIMA by using the capture to fission ratio and the U-235 I enrichment percentage (93 2%). The V, V-Fe, V-Co, and M c-N10 dosimetry wires from the monitor a packages were all later cleaned at one time by etching them individually in a nitric acid solution to remove the outer layer and then weighed. The V-Fe, V-Co and Mgo-Mio wires were then placed in labled 2/5 dram vials for gamma ray spectral analysis to determine microcuries of Co*60 or Mn-54 per milligram at the end of irradiation. The Co-60 activity from the V-Co wires and the Mn-54 activity from the V-Fe wires was used as input to the computer program " DOSE 2" which calculates the corresponding fast and thermal neutron fluence and flux at 100% power. The calculations are based on the reactor power history, the nuclear reaction cross sections, and the initial percentage of the parent nuclide in the wires and this program also uses the Bateman equation to automatically correct for depletion of the target and product atoms.

However, the program only really determines the reaction rate (cross section* flux) for each of these nuclear reactions.

This reaction rate includes contributions from the flux at all different energies. The accuracy of flux and fluence values is thus entirely dependent upon the choice of appropriate cross sections to reflect the various neutron energies present is this particular reactcr. In addition, the flux is dependent on the accuracy of the 5 power values used in the reactor power histroy. The cross sections used in this calculation were take.1 from a memo by D. Matthsws and V. Malakhof to J. Saurwein entitled "FSV Dosi=etry Cross Sections" (FFE :131 : DM/VM: 30, 9-15-80) at the request of V. Malakhof. Since no Ni cross sections were included in this memo; the data-from the Mgo-N10 wires was not used. The power history used in this calculation is based on the FA GUAGE power history for cycles 2 and 3, which is detailed in GA documents 906867 and 907731. The basis for 100% power was taken as time point #559 in cycle 3 bwm92 B-2 ~-

5 3 1 TABLE 1 Monitor Thermal Thermal Fast Fast Fissile FIHA' Fertile FIHA 8 identification Flux Fluence Flux Fluence Heasured Loading' Nominal Loading Heasured Loading (810) (810) ( 810 ') (810**) (5) (5) 8 llote # 18: Honitor #1 9.2 3.8 37 1.55 32. 45. 1.03 lloie f 67: Monitor #1 9.1 3.8 3.9 1.64 31. 39. I.04 liole # 86: Honttor #3 8.8 3.7 4.2 t.76 31. 48. 1.08 7 O N Ilote #131: Monitor fil 9.8 4.1 37 1.52 31. 49. 1.23 Ilole #239; Honitor fil 9.7 4.0 39 1.61 33. 56. 1.21 Ilote #3071 Honitor fl 8.9 37 3.7 1.56 30. 47. 1.05 1 D in 'FIHA was calculated insing this formula $FIHA = 100'D/(18CF8FY8A) (FIHA la Fissions per Initial heavy Metal Atom) Where D - DPH of Cs-137 per milligram or initial heavy metal ~ ~ ~ em 1 - decay constant for Cs-137 - 4.368alo-e CF - Correction Factor for decay and depletion of Cat 137 during irradiation (CF-0.95 for U and 0.97 for Tli) FY - Cs-137 fission yield - 0.062218 for U and 0.068038 for Th A = Ileavy Metal Atoms per milligrases ( A-2.5613 a l o roc 935 enriched U and 2.5961810 ne for Th) "The measured Cs-137' activity in each particle was divided by calculated initial heavy metal loading. The initial heavy metal loading was calculated using this formula: Loading - (4/3)'s'(D/2)'8p'WP o co Where D - diameter of kernel (meastared by x-ray or nominal) p = kernel density - 10.9 mg/use' for UC, and 8.74 for ThC ) 21 WP = fraction of heavy metal in kernel (WP - 0.9073 for UC, and 0.9062 for Thc.) N ( l

908909 N/C i 4 (cont.) APPENDIX B INTERNAL CORRESPONDENCE 8 GA 1076 IN REPLY FROM V. Malakhof REFER Project 1900 y FSV:1447:VM:86 TO T. Crockett DATE June 12, 1986 i 512 JECT Microscopic Cross-sections for FTE-2 Particle Burnup Calculations Per your request, the 1-group microscopic cross-sections for FTE-2 particle burnup calculations were generated as given in Table 1. Also, the uranium isotopic distribution prior to burnup Is given in Table 2. The data In Table I was obtained from the reference FSV fuel management study with the GARG0YLE model. Due to the nature of this model the cross-sections are representative of the whole Segment 3 at the end of Cycle 3, rather than being specific for the FTE-2 burnup. However, I think the Inaccuracy of these calculated cross-sections is not very significant, I.e., they will still provide a valid basis for comparison of calculated and measured results. Nevertheless, be conscious of stated Inaccuracy and try to formulate what Improvement of the cross-section data will result in a better agreement with the measured results. Attachment - Table 1 & 2 cc: D. Alberstein D. Hill W. Lefler F. McCerd / i i 4 I B-4

r-908909 N/C (cont.) APPENDIX B g Y...- INTERNAL C HtESPONDENCE M IM6 9 y ~ TABLE 1 1-GROUP MICROSCOPIC CROSS-SECTIONS BARNS NUCLIDE 6e 6 f 6a Th-232 2.7 0.0 2.7 Pa-233 35.5 0.0 35.5 U-233 11.7 96.3 108.0 U-234 30.9 0.0 30.9 U-235 1'.4 76.5 93.9 U-236

1. 2 0.0 11.2 U-238 9.6 0.0 9.6 TABLE 2 ISOTOPIC OISTRIBUTION OF URANIUM w/o U-234 0.97 U-235 93.15 U-236 0.42 U-238 5.46 L

B-5}}