ML20108C167

Nonproprietary Version of Fluence Calculations for Palisades Plant

ML20108C167
Person / Time
Site:	Palisades
Issue date:	04/01/1996
From:	Avery A, Carolyn Cooper, Wright W AEA TECHNOLOGY
To:
Shared Package
ML18065A679	List: ML20108C167
References
AEAT-0121, AEAT-0121-(NP), AEAT-121, AEAT-121-(NP), NUDOCS 9605060210
Download: ML20108C167 (59)

Text

.

ATTACHMENT 2 CONSUMERS POWER COMPANY l PAllSADES PLANT  !

DOCKET 50-255 l FLUENCE CALCULATIONS FOR THE PALISADES PLANT AEAT-0121 April 1996 l

l 59 Pages

tgeotBas at8Sjh5 P

l

l I

l FLUENCE CALCULATIONS l FOR THE i PALISADES PLANT  ;

l i

l Preparedfor CONSUMERS POWER COMPANY i

Jackson, Michigan l

i April 1996 f

c w 4 f

l19 . + Nun % \-%

Prepared By I Quality Assurance Date

/Date w ppct $/-96 Project Secretary // Date

^'~

AEA Technology l

Engineering Services,Inc.

241 CURRY HOLLOW ROAD PfrTSBURGH, PENNSYLVANIA 15236-4696 (412) 655-1200 FAX:(412) 655-2928 l

2535-4 @ l-00

~

t

. AEAT-0121 Fluence Calculations for the Palisades Plant A F Avery and W V Wright February 1996 NAME SIGNATURE POSITION DATE Author Wendy Wright w,v.gdLV Analyst gg3g iI

/

RPSCD Shielding Checker Alan Avery Consultant RPSCD /2/f/94

/[

Approver Colin Cooper C .k. Cg & p ent so,g Manager. RPSCD__

REACTOR PHYSICS, SHIELDING AND CRITICALITY DEPARTMENT PLANT SUPPORT SERVICES GROUP AEATECHNOLOGY WINFRITH 4

4

l l

l .

This report was prepared as an account of work carded out by AEA Technology in accordance -

with the contract between AEA O'Donnell Inc. and Consumers Power Company dated 10 October 1994.

l l

l l -

i l

The information which this report contains is accurate to the best knowledge and belief of AEA Technology, but neither AEA Technology nor any person acdng on behalf of AEA Technology make any warranty or representation expressed or implied with respect to the accuracy, completeness or usefulness of this infonnation, nor assume any liabilities with respect to the use of, or with respect to any damages which may result from the use of any information, apparatus, method or process disclosed in this report.

l l

I i AEAT-0121 L

i

}

Fluence Calculations for the Pn%h Plant A F Avery and W V Wright

SUMMARY

Calculations of the neutron fluxes in the pressure vessel of the reactor at the Palisades Plant have been carried out on behalf of Consumers Power Company under the contract between that company and AEA O'DonnellInc.The calculations have been performed using the MCBEND Monte Carlo code with nuclear data from the ENDF/B-VIlibrary. Values of the neutron fluxes have been obtained in the surveillance capsules within the vessel and in the cavity outside the vessel as well as at positions through the vessel itself. Calculations have been carried out with the source distributions within the core for cycles 1-4, cycle 5, cycles 6. & 7, cycle 8, cycle 9, cycle 10, and cycle 11, the model being changed to describe the modified fuel assemblies in the last four of these cycles. Measurements of the reaction rates of a range of detectors are available from monitors which were removed from surveillance capsules after cycles 5, 9, and 10, and from the cavity after cycles 8 and 9. 'Ihe calculated and measured reaction rates have been compared and adjustments made to the calculated neutron fluxes in order to improve the consistency between the two sets of values. The fluences are presented in terms of the contributions from neuunns with energies above 0.lMeV and 1.0MeV as well as the displacement rate for iron atoms (dpa).

4 i

AEATechnology Plant Support Services Group Reactor Physics, Shielding & Criticality Department Winfrith Dorchester , _ .

Dorset D12 SDH 1

ji AEAT-0121

)

1 de iii AEAT-0121

i CONTEBfrS g 1 INTRODUCTION 1 2 MODEL DESCRIPTION 1 3 MATERIAL COMPOSITIONS 3 4

4 SOURCES 3 5 CALCULATIONALMETHOD 4 6 MEASUREMENTS 6 7 RESULTS 7.1 Surveillance Capsules 6 7.2 Adjustment of the Survellance Capsule Fluxes 7 4

• l 7.3 Fluxes in the Cavity 8 j 7.4 Adjustment of the Fluxes in the Cavity 8 8 BEST ESTIMATE FLUENCES 9 REFERENCES 12 O

iy AEAT-0121

TABfFR .

I 1 Types of Fuel Elements per Cycle .

2 MaterialCompositions 3 Total Sources used in the Calculations .

4 30 Energy Group Scheme 5 Data for the Detector Foils 6 . Measured Decay Rates ,

l 7 Positions of the Cavity Dosimeuy 8 Results for the Surveillance Capsules at 20 9 Power History

[

10 Calculated Spectral Response of the Monitors in the 20' Capsules 11 Fluxes and Decay Rates in the Capsules after Adjustments 12 Calculated Reaction Rates and Fluxes for the 20" Capsules 13 Calculated Axial Distributions of Fluences in the 20' Capsules

~

14 Calculated Fluxes and Decay Rates in the Cavity 15 Values of C/M in the Cavity .

16 Calculated Spectral Responses of the Monitors in the Cavity for Cycle 8 17 - Adjusted Fluxes and C/Ms in the Cavity 18 Cycles 1 - 4 Combined, Flux >0.1 MeV in Vessel Wall at Mid-height 19 Cycle 5, Flux >0.1 MeV in Vessel Wall at Mid-height 20 Cycles 6 & 7 Combined. Flux >0.1 MeV in Vessel Wall at Mid-height 21 Cycle 8, Flux >0.1 MeV in Vessel Wall at Mid-height 22 Cycle 9, Flux >0.1 MeV in Vessel Wall at Mid height 23 Cycle 10, Flux >0.1 MeV in Vessel Wall at Mid-height 24 Cycle 11, Flux >0.1 MeV in Vessel Wall at Mid-height i

25 Cycles 1 - 4 Combined Flux >1.0MeV in Vessel Wall at Mid-height 26 Cycle 5, Flux >1.0MeV in Vessel Wall at Mid-height 27 Cycles 6 &7 Combined, Flux >1.0MeV in Vessel Wall at Mid-height 28 Cycle 8, Flux >1.0MeV in Vessel Wall at Mid-height AEAT-0121 v

29 . Cycle 9. Flux >1.0MeV in Vessel Wall at Mid-height 30 Cycle 10, Flux >1.0MeV in Vessel Wall at Mid-height 31 Cycle 11, Flux >1.0MeV in Vessel Wall at Mid-height j

32 Cycles 1- 4 Combined, dpa/s in Vessel Wall at Mid-height 33 Cycle 5, dpa/s in Vessel Wall at Mid-height 34 Cycles 6 & 7 Combined, dpa/s in Vessel Wall at Mid-height 35 Cycle 8, dpa/s in Vessel Wall at Mid-height 36 Cycle 9, dpa/s in Vessel Wall at Mid-height l 37 Cycle 10, dpa/s in Vessel Wall at Mid-height 38 Cycle l l, dpa/s in Vessel Wall at Mid-Height 39 Fluence to End of Cycle 11, Flux >0.1MeV in Vessel Wall at Mid-height 40 Fluence to End of Cycle 11, Flux >1.0MeV in Vessel Wall at Mid-height f 41 Exposures to End of Cycle 11, dpa in Vessel Wall at Mid-height I

I .

l l

l I

I i

l AEAT-0121 vi

.. . . . . . . - - . - -. - - . .=. _- . .- . - . - . _ . _ , _ .

FIGURES . .

1 Scan Down the Paha sReactor 2 Plan View Across a Quarter Section of the Palisades Rextor 3 Arrangement of Fuel Elements in the Rextor Core 4 Section Across a Fuel Element with 216 Fuel Pins .

5 Fuel Element Arrangement (a) 208 fuel pins in assembly (b) 208 fuel pins with 8 hafnium rods (c) 152 fuel pins with steel rods on one side (d) 160 fuel pins with steel rods on both sides (e) 194 fuel pins with steel rods in corners ,

l 6 Drawing of Surveillance and Accelemted Capsules s .

vii AEAT-0121

. 1 INTRODUCTION l

l Calculations have been performed on behalf of Consumers Power Company to provide i values of the neutron fluences in the surveillance capsules and the pressure vessel of the l Palisades plant in order to assess the propeny changes that will be induced by neutron l '

irradiation, ne reactor has recently completed its lith cycle of operation, and the

! fluences have been obtained based on actual power histories, core loadings, and source l

distributions for these cycles. Fluences have been derived at the irner and outer surfaces of the vessel and at quarter, half and three-quaner distances through the vessel at the core centre-plane and at 450mm below the centre. plane. Steel specimens have been irradiated in surveillance capsules located inboard of the vessel and fluences are l provided at these positions in order to relate the measured property changes in the l samples to those that are expected in the vessel itself. Measurements of the reaction rates of a number of detectors have been made in these surveillance capsules and also in dosimetry capsules located in the cavity between the vessel and the pnmary shield. De calculations include predictions of these reaction rates thus enabling their accuracies to be assesed through comparisons with the measurements.

The geometrical model which was developed for this work was ba. sed on drawings of the Palisades plant provided by Consumers Power Company. The calculations were carried out usmg the radiation shielding code MCBEND9A (1) and nudea- data from ENDF/B-VI processed into the DICE format in 82".0 energy bands (2) for use with this code. The code and the data have been validated for use in this type of calculation by comparisons of measured and predicted reaction rates in the H B Robinson PWR and in the NESDIP 2 simulation of a PWR shield (3).

ne calculations were performed under the contract between Consumers Powe'r l Company and AEA O'Donnell Inc dated October 101994 MODEL DESCRIPTION 2

l A three-dimensional model of the reactor, based on the engineering drawings provided, i

was created for use in the MCBEND code. The geometry was set u? using the PG (fractal geometry) facility in MCBEND (1). Advantage was taken of tae symmetry of l the reactor so that a 90* sector was modelled with reflection planes at the azimuthal

boundaries. Since calculations were only required at radial positions close to the core l centre plane it was not necessary to include detailed representations of the components at the top and bottom of the core.

1 l A vertical section through the model of the Palisades reactor is shown in figure 1 whilst l a plan view across the core is shown in figure 2. Azimuthally a quarter section of the reactor was modelled extending radially to include the first 50cm of the concrete shield, the lauer having an inner radius 335.92cm with a 0.64cm thick mild steel liner inside this. In the axial direction it extended from the centre line of the nozzle above the core to 50cm into the base concrete. The reactor core is composed of 204 fuel elements of 366.95cm overall height and 335.28cm active length. The core is surrounded laterally by the core shroud of 1.59cm thick steel and the core barrel. The shroud is stepped to form a wrapper around the fuel assemblies while the banel is a steel cylinder of height 570.41cm with outer diameter 387.98cm and thickness 3.81cm. Between the core

! barrel and the shroud there are eight horizontal support plates of 3.81cm thick steel spaced at intervals of 44.45cm, the base of the lowest plate being at 163.59cm below the centre plane of the active core. De carbon steel pressure vessel is formed of a cylinder of wall thickness 21.59cm and outer diameter 481.34cm, the inner surface being lined with 0.64cm stainless steel. De vessel has a dome-shaped base with its centre at 231.80cm below the core centre line. Outside the pressure vessel there is a similarly shaped insulation layer of thickness 10.16cm with outer diameter 505.46cm over the barrel section and outer radius 257.97cm over the domed base. These features l 1 AEAT-0121

i 1'

~

i viere represented explicidy in the model as shown in figures 1 and 2. (Later data which became available after completion of the calculations showed that a more accurate value f

for the as-built thickness of the vessel barrel would be 0.76cm (0.3 inches) greater than l

the 21.59cm (8.5 inches) specified in the model ne effect of this difference'is  :

consideredin Section 7.4 below) l s' .

De arrangement of the fuel elements within one quaner of the core is shown in figure I

3, the elements being numbered according to the reactor scheme;ney are square in cross-section (20.955cm x 20.955cm) in a symmetric arrangement with attemating i

4 gaps of 0.2667cm and 0.9322cm separatmg most elements. De gap along the.' . ,

symmetry planes is 0.9322cm. The exceptions to this regular pattem are the elements in l

the outer rows of three (numbers 8,16, 24 and 49, 50, 51) which are separated from i each other by 0.2667cm gaps. In modelling the core the gaps between assemblies were reproduced explicidy.

. i i

i ne plan views across a fuel pin and a fuel element with 216 fuel pins are shown m i figure 4. De fuel element is composed of a 15 x 15 array of pin positions with the central position being filled by a guide tube, and 8 others being occupied by guide rods,-

j* there being two in the outer row of pins on each side of the assembly. Other fuel assemblies contain only 208 fuel pins with a further 8 pin positions being occupied by 1

I guide tubes. This armngement is shown in figure Sa. The pin pitch is 1.397cm and '

! cach pin is composed of uranium oxide pellets of diameter 0.89cm with zircaloy-4 j cladding of outer diameter 1.06cm and thickness 0.075cm. The height of the active length of the fuel is 335.28cm with inactive regions in the assemblies of height i 21.06cm at the top and 10.61cm at the base.

e The numbers of 216 pin and 208 pin assemblies forming the reactor core varies from l

d cycle to cycle. In addition for cycles 8 to 11 some of the pin positions were occupied by

' hafnium or steel rods in selected peripheral assembhes. Plan views across the j- arrangements of the special assemblies are shown in figures 5b to Se whilst the core loading for each cycle is shown in Table 1. For cycle 8 fuel assemblies with four rows 4

of steel rods as shown in figure Sc were loaded into locations numbered 8, 38, 48, and l 49 in figure 3, with corresponding loadings in the other quadrants. In cycle 9 these four

- positions were occupied by fuel assemblies with hafnium rods as shown in figure 5b.

j_ For cycle 10 assemblies with hafnium rods were loaded into positions 24, 38, 48, and 51 while assemblies with the pattem of steel rods shown in ngure 5d were installed in locations 8 and 49. For cycle 11 the assemblies with steel rods at their comers as .

shown in figure 5e replaced those with hafnium rods in cycle 10. and the assemblies with steel rods along two sides were retained at locations 8 and 49. For the inner core the matenals within the active length of each assembly were smeared over the ,

corresponding volume. For those assemblies at the edge of the core the modelling was more detailed with the materials being smeared over exh pin cell to give appropriate compositions for cells containing fuel, guide tubes, guide rods, or steel rods. .

The surveillance capsules have been modelled as rectangular steel rods 3.89cm x 1.95cm in cross-secnon and 366.95cm in height located centrally in a 4.92cm x 3.21cm '

x 366.95cm water filled enclosure of 0.305cm thick steel, as shown in figure 6. De '

capsule was situated at the 20' position just inside the pressure vessel wall, with its centre at a distance of 214.63cm from the core axis, and it was present in the - I calculations for all cycles. An accelemted capsule, modelled as for the surveillance capsule, was present in the model for the calculations for cycles I to 5, being located on the outer surface of the core barrel at the 30' position with its centre at 19619cm from  :

i the core axis. (He azimuthal angles defimng these positions are measured in a clockwise direction relative to the 0 axis shown in figure 2.)

Scoring regions were set up in which the Monte Carlo calculation gave mean values of the fluxes and reaction rates. For the surveillance capsules these were axial regions of 50cm length in the steel representing the samples. In the vessel wall scoring regions of 2 AEAT-0121

~-

)

i , ,

50cm height,5* angle and lem thickness were set up at positions at quarter, half and -

three-quarters penetration and at the outer surfxe. At the inner surface scoring was in l

similar azimuthal and axial intervals over the thickness of the vessel liner. Fluxes and reaction rates were also scored in the cavity at the posidons of the dosimetry capsules.

For cycle 8 the scoring regions were at the nominal radul position of 108 inches (i.e.

l having boundaries at 273.82cm and 274.82cm) with heights of 50cm and azimuthal '

4 j angles of 55 More detailed scoring regions were included in the model for cycle 9 to take account of the variation in the radial positions of the detectors at various azimuthal angles. Icm thick scoring regions were therefore set up with inner radii at 255.28cm.

. 257.56cm,259.85cm,26239cm,266.96cm and 273.82cm, the heights again being 50cm and the azimuthal extents being mostly 5*. l i

l 3 MATERIAL COMPOSITIONS l

I ne compositions of the materials used in the calculations as derived from data supplied ]

by Consumers Power (4) are listed in Table 2. De density of the core water and that of ,

the water between the core shroud and banel was 0.754g.cm ', and that of the  :

downcomer water was 0.767g.cm '. He densities of the fuel element smears were derived from the table of the masses of materials la the active lengths of the assemblies (4) (5). For the inner fuel assemblies the matenal was smeared over the whole assembly. For the twelve outer fuel assemblies in the 90" sector, i.e. those with i surfaces adjacent to the core shroud, the materials of the fuel pin were smeared with the  !

i

! water over one pin pitch with the guide tubes, guide rods, steel rods and hafnium rods )

being treated in a similar way. l l

4 SOURCES J Average pin powers for each cycle, pin powers at 5 time steps through each cycle and combined mean pin powers over cycles 1 to 4 and 6 to 7 were supplied by Consumers i Power (5). The pin powers for each fuel assembly were given together with their axial  !

1 variations in 25 equallengths over the height of the core. He fractions of the fissions occuning in uranium and plutonium were also supplied for each assembly for the same time steps. He calculations were canied out for a full reactor power of 2530MW (5).

The source in each pin is derived from:

(2.432f,, + 2.88f% )

Source /cm3A1= xP.r (3.242E-17 x uf )+(3.385E-17 x fu) where P is the pin powerin MW, r is the axial profile factor for the assemb'

, _A.is the pin area, 1is the active fuellength, fu the fraction of fissions in uranium and fPu the fraction of fissions in plutonium.

The weighting factors 2.432 and 2.88 are the numbers of neutrons per fission for thermal neutron fission in U* and Pu2 " taken from ENDF/8-VI, while 3.242E-17 and 3.385E-17 are the corresponding useful energies per fission (MW) taken from the i compilation of James (6).

48 l - - u

- - ~ -- . - - . - - - - . - - - - - - - . -- . . . _ . . ..

P. the pin power in MW,is given by:

P= .p n

where n is the number of pins in the mactor and p is the pin power which was normalised to a mean value of unity over the whole core in the distributions provided -

by Consumers Power.

t For most of the fuel elements the source has been averaged across the area of the fuel .

element. For the fuel assemblies close to the periphery of the core, namely numbers 8, 16,23,24,31,36,37,38,43,46,47,48,49, 50, and 51 in figure 3, the source has '

been re presented in greater detail. For cycles 1 to 7 the sources were averaged over a 3 x 3 fuel pin mesh except for the outer three rows of pins adjacent to the core shroud.

For these rows the interval for the source mesh was one pin cell in the direction perpendicular to the outer surface so that the areas were 3 x 1 pin mesh in most i assemblies but 1 x 1 pin mesh at the comers of the core in assemblies 24, 38, 48, .nd 51 which have two external surfaces. Similar approaches were followed for the other cycles but the boundaries in cycles 8 and 10 were adjusted slightly to take account of l the absence of sources in the steel pins. The calculations are more sensitive to the power distributions in the outer assemblies and the latter show greater variations across an assembly so that the use of the finer mesh enabled the sources to be represented in i detailin the important regions. Separate calculations were performed for the sources in )

the inner and outer assemblies with single axial profiles being applied in each case.

Rese corresponded to the mean axial profiles for the two sets of assemblies.

De fraction of the source neutrons ansing from fissions in plutonium for each -

assembly was calculated from:

2.88fs '

2.88f3 + 2.432fy where fPu is the fraction of fissions for plutonium andUf is the fraction of fissions for uranium in the assembly.

The total sources for each cycle or combination of cycles used in the calculations are 4 shown in Table 3.

2 2  !

The spectra of neutrons arising from fission in U " and Pu " were genemted by the in-built capability of MCBEND, and sampled using the appropriate fmetions for the  !

contributions of the two isotcpes to obtmn the variation of the total source with energy.

5 CALCULATIONAL METHOD ,

ne calculations were carried out using version 9A of the Monte Carlo code MCBEND (1) with data taken from the ENDF/B-VI neutron cross-section libmry (2). He reaction rates were calculated using the IRDF-90 cross-sections (7) for the detectors and the data from ASTM Standard E693-79 for the dpa rate, these being held in all cases in the 640 -

energy groups of the SAND II scheme. The code and data are maintained to a level of quality assurance consistent with the standards of the ANSWERS Software Service of AEA Technology. This ensures that teference versions of the code, data libraries and test data are held, and that updating and archiving of the code and data are strictly controlled.ne neutron fluxes were calculated in a standard 30 group energy scheme as shown in Table 4.

4 AEAT-0121

q i

~

l The quanddes ofinterest are the neutron fluences above 0.lMeV and 1.0MeV. and the j -

displacement rates per atom in iron (dpa) in the vessel at the com centre plane and in the cucumferentialweld at about 4Sem below the core centre. They were calculated at the ,

i inner and outer surfxes of the vessel, and at penetrations of one quarter, one half, and l three-quarters of the wall thickness through it. Dosimetry reaction mies for all cycles were calculated for the surveillance and accelemted capsules for the reactions

- Cu63(n,a)Co60, pe54(n,p)Mn54, NiS8(n.p)CoS8, U238(n.f)X and Tie 6(n.p)Sc4 6. For l cycle 9 the reaction rates for Co59(n,y)Co60 and Np237(n,f)X were also obtained in the j surveillance capsule although these have not been included in the later analysis. For j

- cycles 8 and 9 dosimeuy measurements had been made in the cavity between the vessel  ;

and the primary shield with Cu63(n a)Co60, pe54(n p)Mn54, NiS8(n.p)CoS8, ]

U238(n,f)Csl37, Ti46(n,p)Sc46, Nb93(n n')Nb'3=, CoS9(n,y)Co60 and l l

Np237(n,f)Csl37, and the reaction mtes for these detectors were therefore calculated in the cavity regions. De calculated reaction rates for Co" have not been used in the l subsec uent comparisons with measurements because of the sensidvity of the values to l the ratier uncertain composition of the concrete primary shield, and the low relevance  !

7 of the neutrons to which this detector is sensin,ve in assessmg the accuracies of the j l

1 fluxes at higher energies which are important for radiadon damage. De fluxes and the '

. reaction rates were scored by track length estimation to give the mean values over the volumes described in Section 2 above. The detailed pattern of scoring regions within i the cavity for cycle 9 enabled the reaction rates to be entalaH at the positions of the i detectors.The distributions within the cavity also gave factors which could be applied '

to allow for the differences between the true positions of the detectors and the nominal L position of 108 inches from the core axis for cycle 8. l t

! For convenience in specifying the source distribudons the calmtarions were performed .

t separately for theinner(numbered 1, 2, 3, 4, 5, 6, 7, 9, 10, 11, 12, 13, 14, 15, 17 ]

l 18,19, 20, 21, 22, 25, 26, 27, 28, 29, 30, 32, 33, 34, 35, 39, 40, 41, 42, 44, 45 in l figure 3) and outer (8,16, 23, 24, 31, 36, 37, 38, 43, 46, 47, 48, 49, 50, 51) fuel

- elements, and the results combined. Calculations were performed for sources from l cycles 1 to 4 combined, cycle 5, cycles 6 and 7 combined, and for cycles 8, 9.10 and l

11. Cycle 5 was calculated separately because it preceded the removal of dosimetry l i

from the surveillance capsule and would thus have a major effect on many of the ,

! calmiarad activations of the detectors. When calculating the integrated fluences for '

several cycles it is possible to use the avemge source distributions for those cycles, but mrae detailed consideration is needed for the reaction rates of the short-lived isotopes (e.g. Co" with its halflife of 70.8 days) because these will only be sensitive to the

fluxes in the year before removal. In an inidal study three calculations were performed

! for cycle 8 for the disuibution of pin powers at the beginning, middle and end of the cycle (referred to as times 1, 2 and 3) and activations of the detectors were calculated using the time-dependence of the reaction rates through the cycle. However the differences between this approach and the use of cycle-averaged reaction rates were 1

about 1% so that time dependence of the source distribudons within a cycle was not included in any of the other calculations. For cycles 5, 9,10 and 11 therefore the average pin powers over each of the cycles were used Dere were significant diffeirences m the arrangement of the pins in the peripheral sub-assemblies for cycles 8, 9,10, and 11 which necessitated separate treatments for each. For cycle 8 the sensitivity module in MCBEND was used to obtain the mies of change of the calculated

(

fluxes and reaction rates with changes in the cross-sections. These could then be combined with the co-variance data for the cross-sections to derive the uncertainties in the predictions due to uncertainties in the cross-sections.

I The acceleration of the MCBEND calculations was achieved with splitting and Russian roulette together with automatic weighting of the source. The importances were ,

1 calculated in an initial mn using the MAGIC option of MCBEND.

5 AEAT-0121  ;

N

~ ~

6 MEASUREMENTS j . .

Measurements had been made of the reaction mies of a number of detectors that had i

been irradiated in surveillance capsules located at the 20* posidon. Dosimetry packs j were removed at the end of cycles 5,9, and 10, the detectors having been irradiated

over all preceding cycles for the first and last of these, but only for cycle 9 for the

other. Dosimetry packs were also irmdiated in the cavity outside the pressure vessel at a -

number of azunuthal positions in cycles 8 and 9. Details of the detectors are i summarised in Table 5. De values of the decay mies of the reaction products were measured and presented as dps/gm of foil material corrected to consistent dates for the . .

four sets. These were 27 June 1984,12 December 1990, 4 March 1992, and 12 October 1993 respectively for the measurements after Cycles 5,8,9, and 10. Values of the decay rates as supplied by Consumers Power are given in Table 6, these being the measurements made at the centres of the capsules for detectors other than the fission foils. The table also includes the reference numbers for the capsule and for the individual monitor foils on which the quoted reacdon rates are based. Where several

detectors of the same type were counted the value given in Table 6 is the arithmetic mean. For U2"(n.f) the values given previously have now been corrected for U2 n 2

impurities, photofission and the build up of plutonium, whilst for Np "(n,f) the measurements have been corrected for photofission (8). Values of the mean saturation reaction rates for the fission detectors after being corrected are given in reference 8, but i

~

the individual correction factors for each detector are not available. The saturated values have been converted into decay rates on the specified dates for inclusion in Table 6 by applying in reverse the formula that was used in the averaging process. Values of the  ;'

parameters in this formula were taken from reference 8. The original measurements were made by determining the decay rates for three different fission products in each case, but the results presented in reference 8 are mean values of the fission rates. It is -

not possible therefore to derive the individual activities measured for the three isotopes 5

and the results are shown in Table 6 for U2"(n f)Cs " only as being typical for all of them. (The values of the ratio of " Calculated Activity"/" Measured Activity" (C/M) are independent of the choice ofisotope for converting from saturation acdvity to measured activity.)

ne positions at which the dosimetry packs were irradiated in the cavity are summarised in Table 7. He support bar from which they were suspended was misaligned so that i the capsules at 6' were closer to the vessel than those at 39' by ll7mm. De angular l i

positions are given relative to the O' axis shown in figure 2.

1 7 RESULTS 7.1 Surveillance Capsules l

ne results of the calentation for the fluxes and activities of the detectors in the surveillance capsule are presented in Table 8 together with the measured decay rates and i the ratios of caculation/ measurement (C/M).The values of the fluxes and the dpa rates ~

are those-for the last cycle of the irradiation. He c'alculated activity at the specified time for the measurement of a given detector has been derived using the power history of the reactor as given in Table 9 together with the data for the foils as summarised in Table 5 -

and takes account of the contributions ansing from each of the cycles for which the detector was irradiated.The values of C/M mnee from 0.86 to 1.21. However it can be seen that there is a consistent pattern for each capsule. He C/M ratios for the Fe, Ni, and U2 " monitors are about 25% highet shan those for Cu in all cases while those for Tilie between the values for Cu and that for the other three detectors. The energy ranges to which the reactions are sensitiva are shown in Table 10 which gives the percentage contributions to the reaction ra's.s for neutrons in each of the energy groups.

It can be seen that Cu shows the greatest response to neutrons at energies above 6MeV whilst the Fe, Ni and U are more sensitive to neutrons below 3.68MeV. He 6 AEAT-0121

I i

contributions to the Ti reaction rate are mosdy in the range 3.68 to 10 McV. This  !

suggests that the calculated neutron specuum is in error with fluxes being too low at energies above 7.8MeV and too high in the range 0.82MeV to 3.68MeV. In addition to the reladve values of C/M for the five detectors there is also a varianon from capsule to capsule in the absolute values for a given detector which suggests that the accuracy of the specified source strengths varies. There is however no consistent trend in C/Ms with the half-lives of the detectors; the Ni and Fe rextion products with their differing half-lives of 70.8 days and 312 days show identical C/Ms which indicates that the time dependence of the neutron fluxes is being treated in sufficient detail. In these

. circumstances the application of an adjustment procedure to improve the agreement between measurements and calculations is justified.

7.2 Adjustment of the Surveillance Capsule Fluxes ne code SENSAK(9) has been applied to the fluxes calculated at the surveillance capsules in order to adjust the values to bring the predicted reacdon mies into closer agreement with those that were measured. De code follows the procedure given in ASTM Standard E 944 in which a maximum likelihood approach is applied. The fluxes and the detector cross-sections were specified in the 30 gmup scheme of Table 4.

Uncertainties of 5% were attributed to the measurements as specified for the dosimetry removed after cycle 5. De contributions to the uncenainues in the calculated flux spectra arise from the fission source spectrum, the malenal cross-sections, the density of the coolant, the dimensions of the reactor, and the Monte Carlo stadstics. Following the analysis for the simulated PWR shield in the NESDIP 2 expenment (10) an uncertainty of 3.5% is estimated to arise from the fission spectrum. Sensitivity calculations were carried out for the dependence of the reaction rates upon the cross-sections of the materials and folded with the co-vanance data from the data library. (For hydrogen and oxygen there are no co-vanances in ENDF/B-VI so that data from ENDF/B-V were used for these elenents.) He resulting uncertainty on the reaction  !

rates was 2.4%. An uncertainty of 2% is estimated for the density of the coolant and the sensitivity calculations showed that this was equivalent to a 5% uncertainty in the reaction rates. The uncertainty in the inner radius,of the pressure vessel is 0.25 inch (11) which translates into 4.5% in the reaction rates when this is converted into an equivalent change in the thickness of the water between the core and the ' vessel and the calculated sensitivities are applied. The combination of these effects leads to an uncertainty of tS% to be added to the statistical uncertainties on the group fluxes. The laaer range from 4% in the groups between 1.74MeV and 6.07MeV to 20% in the group between 10.0MeV and 12.0MeV. The standard deviations on the detector cross-sections were taken from the IRDF90 files. An uncensinty of 5% was applied to the source strength, this being the estimated accuracy of the powers specified in the peripheral fuel assemblies. Correlation factors of 0.5 and 0.25 were applied to the group fluxes for the adjacent and next-adjacent groups following the recommendation of McCracken (9). The fluxes in 30 energy groups from the results for cycles 5, 9, and 10 were fed as input to the three SENSAK runs together with the corresponding values of C/M for the detector decay rates from Table 8. Application of the SENSAK code led to increates in the fluxes in the high energy groups coupled with reductions in those at lower energies. Source normalisation factors of 0.98,0.96, and 0.99 respectively were derived for the calculations for cycles 5, 9, and 10. The adjusted results are summarised in Table 11. It can be seen that the values of C/M after adjusunent are mostly within 5% of unity, this being the standard deviation assigned to the measurements. He exceptions are the reaction rates for Cu after cycle 5 and Ti after cycle 9. De uncertainties are those assigned to the, adjusted values by the SENSAK code taking account of the degree of agreement between the measurements and the ,

modified calculations. Table 12 gives the reaction rates and the fluxes in the i surveillance capsules for each of the seven time periods for which calculations were performed.The reaction rates are those which were used when deriving the xtivations i of the detectors as presented in Table 8. (The activations are the decay rates of the detectors at a specific date after removal from the rextor and they take account of the 7 AEAT-0121

_- . ~. - -.- - . - - . - . - - - - _ _ - . - - _ - - . _ - - -

contributions from activadon during each cycle for which the detectors were irradiated and of the subsequent decay.The reaction rates in Table 12 give the rates of production of the active isotopes which are used when calculating these contributions. Dey correspond to the acdvations that would be produced if the reacdons were saturated with zero decay.) In addidon Table 12 includes the fluences for each period derived from the fluxes using the equivalent full power seconds (EFPS) from Table 9 for each cycle.Dese fluences are also presented as the cumulative values through the operation

. of the plant to date. Finally Table 12 includes adjusted values of the cumulative fluences obtained using mean values of the adjustment factors for each of the responses 90.1MeV, pl.0MeV and dpa (see Section 8 below). Table 13 gives the axial .

variation of the fluences integrated over cycles 1 to 11.

7.3 Fluxes in the Cavity De results for the calculadons of the fluxes and reaction rates in the cavity for cycles 8 and 9 are summarised in Table 14. De results for cycle 9 were calculated at the positions of the dosimetry packs; those for cycle 8 were obtained at the nommal radius -

of 108 inches and converted to correspond to the positions of the measurements by multiplying by the ratios from the calculated pattem of reaction rates in the cavity for cycle 9. The factors for correedng for the change in posidon ranged from 0.97 to 1.15 which is indicadve of the variation in a maction rate with radial )osition within the cavity, and also of the uncertainty arising when the posidon of tie detectors is not known accurately.ne ratios of calculations to measurements are summarised in Table

15. Here is again a trend in the C/Ms with the values for Fe, Ni and US tending to be higher than those for Cu, although it is not so marked as was the case for the surveillance capsules, and is completely absent for the results at 39" for cycle 8. In the later comparison the values of C/M lie between 0.96 and 1.06 with no consistent -

]

1 variation with the energy range to which the detectors are sensitive. For the remainder the mean ratio between the C/Ms for Cu and those for Fe and Ni is 0.9 com 3ared with the corresponding value of 0.8 for the surveillance capsules. He shape of tie neutron -

spectrum is thus piedicted more accurately for the cavity dosimetry than it was for the capsules. However the overall mean value of C/M is 1.14 when all of the results in Table 15 are included. which can be compared with the corresponding mean of 1.06 for the surveillance capsules.

De energy distributions of the contributions to the reaction rates in the cavity are presented in Table 16 for three azimuthal positions for cycle 8. He neutron spectrum is softer than it is in the surveillance capsules with 30% of the U2 reaction rate arising from neutrons with energies below 1.74MeV compared with 14% for the posidons inside the vessel. Correspondingly the fracdon of the 11ux at energies above 1MeV which is below 1.74MeV is 63% in the cavity compared with 30% in the surveillance capsules. De US reaction rate is thus more unponant as an indicator of the accuracy

.of the calculated pl.0MeV in the cavity than it was in the capsules.

7.4 Adjustment of the Fluxes in the Cavity The3ENSAK code has been used to adjust the neutron fluxes in the cavity following a similar procedure to that adopted when modifying the results for the surveillance capsules. The uncertainty to be added to the statisdcal uncenainties for the group fluxes -

was increased to 21%. This was due to the addidonal contribution of the uncertainty in the calculated attenuation by the pressure vessel arising from the co-variance data for the cross-sections of iron, a tolerance of 0.25 inches on the thickness of the vessel (11),

and the sensitivities of the reaction rates to the iron cross-sections. He stadstical uncertainties on the group fluxes were between 1.8% and 6.3% for the energy range between 0.01MeV and 10MeV withlarger uncertainties for the groups above this. De uncertainties for the measurements with the U23 and Np237 fission foils in the cavity were relaxed from 5% to 10% in view of the large differences between the C/Ms for the two detectors in the results for cycle 8.The adjusted values of p0.1MeV, pl.0MeV, 8 AEAT-0121

l and the dpa rate together with the modified C/Ms are summansed in Table 17. De adjusted values of C/M are mostly within 1% of unity with a few showing discrepancies of 2% and 3%. He values of $>l.0MeV are reduced by factors in the range 0.78 to 0.97 with the adjustments leading to smaller changes for 9>0.lMeV and the dpa rate. He uncertaindes on the adjusted quantities am mostly close to those assigned to the measurements although where there is consistency across the detectors as in the results at 39' for cycle 8 they are reduced. Conversely they am increased above the standard deviations specified for the measurements where the SENSAK code recogmses mconsistencies.

After completion of the calculations it was found that a more accurate value for'the as-

! built thickness of the vessel would be 8.8 inches instead of the 8.Sinch thickness that l was used in the model (12). He difference is just greater than the 0.25 inch standard i deviation assumed in the SENSAK adjustments. However increasing the uncensinty to

cover this would give an ovemil standard deviation of 24% for the calculated reaction l rates instead of the value of 21% used above. As most of the adjustments in the cavity are less than 21% it is not expected that an increase of 3% in the uncertainty would change the results significandy. It is estimated that ca incmase of 0.3 inches in the vessel thickness would reduce the rextion rates for energies above 1MeV by 18%

which would give a mean C/M for the cavity of 0.96 instead of 1.14. However the decreases in the reaction rates which have been generated by SENSAK will be correcting for this errorin the thickness as indicated by the mean reduction of the C/M by 15% for the high energy reactions (i.e. omitting the Np*(n.f) detector since it also responds to lower energy neutrons). Because they have been adjusted to be consistent

! with measurements the results from SENSAK will thus correspond to the true vessel thickness.

8 BEST ESTIMATE FLUENCES The fluxes and reaction rates following adjustment by SENSAK as given in Tables 11 and 17 represent the best estimates of thosc quanuties for the quoted positions and cycles. De measur:ments on which they are based however, are available for a restric:ed number of positions and irmdiation periods. Thus there are only measurements in the cavity for cycles 8 and 9 while the surveillance capsule results refer only to the 20* azimuthal angle. He adjustments to the fluxes are made to allow for errors in the calculations so that the lauer are modified to be consistent with the measurements.The nature of these errors determines the way in which they will affect the results at different times and positions.  ;

Errors in the source data may be expected to vary from cycle to cycle especially when the configurations of the important fuel assemblies la the peripheral locations differ. In absolute terms such errors will tend to affect positions at all penetrations through the vessel equally, but variations in the accuracy of the disuibudons within the outer assemblies will give an azimuthal dependence of the errors arising from the source data.

, Errors in the material cross-sections and the fission spectrum will give errors in the calet11alea fluxes which will be independent of time. Dey will however be funcdons of the thicknesses of the matenals which have been penetrated; corrections due to shortcomings in the cross-sections for iron for example would be higher at points outside the vessel than at those on the inner surface.

Errors in the dimensions of the vessel will not vary with time but could depend upon position. Therefore adjustments made on the basis of measurements made in one octant of the reactor would not necessarily apply in the other sectors.

9 AEAT-0121

Enors in the density 6f the coolant could change from cycle to cycle but for a given l

cycle the errors in the fluxes resulting from this source would be expected to be l approximately similar at any point within the wall of the vessel or in the cavity. '

The statistical uncertainties of the mimhdons lead to errors which will vary both with position and cycle, although these have been reduced to levels where their contributions l -

are small compared with those ansing from the other sources.

3e errors can thus be classified as being dependent on time and position either separately or in combination. The measurements for cycles 8 and 9 give evidence of the accuracy of the Mmbdons at specific positions for single core source distributions.

The monitors withdrawn with the surveilance capsules after cycles 5 and 10 give data relevant to the fluxes in the capsules for all preceding cycles, but this is restricted to the rl

.lonp(n.p)ived Ti detectors.

Sc*' (half-life De reactions 83.8d), Ni"(n.p)Co" with Uthe (half life 70.8d). shorter-lived groducts suc (n.f)Zr"(half-life 64.2d), and U2 "(n,f)Ru'"(half-life 39.4d) vill only provide data for the cycle immediately preceding removal. He overall period for cycles 1-5 is nearly 13 years so that it would only be U "(n.f)Cs " (half-life 30.2y) and to a lesser degree Cu"(n a)Co"(half-life 5.26y) which would be sensitive to the early cycles. Similarly for the capsules removed after cycle 10 the total elapsed time of the irradiation is 22 years with cycle 9 finishing 484 days before the end of the irradiation. Moreover the U2" measurements have been rejected from this dosimetry so that the data are mostly relevant to cycle 10 only.De adjustment of the fluxes using the full range of detectors as described in section 7 above is therefore dominated by the cycle preceding the removal of the monitors and it was based on the neutron spectra for those last cycles. It l

is therefore necessary to extrapolate the conclusions in order to derive best estimates for the other cycles. ,

1 The adjustment factors from Table 11 for the three sets of dosimetry were as follows: ,

I

$>1.0MeV dpa j

$>0.1MeV l

1 Cycle 5 0.93 (7.2%) 0.91 (7.2%) 0.93 (5.5%)

Cycle 9 0.90 (10 %) 0.85 (9.9%) 0.86 (7.5%)

Cycle 10 0.98 (8.8%) 0.96 (9.2%) 0.95 (6.7%)

Mean 0.94 0.91 0.91 The standard deviations quoted above for the cycle data are those calculated by the

' SENSAK code from the consistency of the results. The mean values are adopted for '

scaling the results calculated for $>0.1MeV, $>1.0MeV, and the dpa rates at the front I of the vessel These averages are considered to be the best estimates of the corrections for the time-in4=Nt errors which arise from the nuclear data and the fission spectrum.The uncertainties assigned to the factors indicate the degree of confidence that can be placed in the adjusted spectra; a value of 10% is conservatively adopted for .

l thisuncertainty when applying the mean factors as corrections for the vessel fluxes.

l The time <iependent uncertamties identified above as arising from the source data, the coolant density, and the Monte Carlo statistics must be added to this. From the

• distributions of the adjustment factors for the three cycles the standard deviation for the variation with cycle is close to 5% for each of the quantities. This is less than the standard deviation of 7% to 8% obtained when the individual uncertainties estimated in section 7.2 for the time-dep,endent quantities are combined. Fmally there is the uncertainty due to the change m position to different azimuthal locations on the vessel surface. Contributions to this arise from the departure of the pressure vessel radius from its specified value and the azimuthal variation of the neutron source strength in the core. Rese were estimated in section 7.2 to be 4.5% and 5% respectively. He total 10 AEAT-0121

standard deviation on the adjusted fluxes at the front surface of the vessel is thus 13%

from the sum of 10%,5%,4.5%, and 5%.

He adjustment factors from Table 17 for the fluxes in the cavity are summarised below.

$>0.1MeV $>l.0MeV dpa Cycle 8 16' 1.0 (7.3%) 0.91(5.0%) 0.97(5.5%)

26' O.97(9.1%) 0.85(4.0%) 0.94(6.8%)

39* 1.0(4.3%) 0.97(5.9%) 0.99(3.8%)

Cycle 9 16* 0.89(6.1%) 0.84(9.5%) 0.87(7.2%)

26' O.93(9.2%) 0.87(4.6%) 0.92(6.9%)

39' O.96(10.2 %) 0.78(10.1 %) 0.88(7.5%)

Mean 0.96 0.87 0.93 He mean factors for $>0.1MeV and dpa are close to those for the surveillance capsules with that for $>l.0MeV being 4% lower. This suggests that the calculation of the attenuation of the three quantities by the pressure vessel is performed with no significant deterioration in the accuracy. De factors which were applied to the fluxes at the inner surface are therefore extended to cover all posidons within the steel of the vessel. The uncertainties on the adjustment factors for cycle 8 are smaller than the values for the surveillance capsules while those for cycle 9 are closer to the uncertainties at the inner position. The uncertainties on the adjusted fluxes in the vessel due to the contributions considemd above for the inner surface are therefore retained at 13% over the full thickness There is however a further contribudon which must be added to this unceruinty of 13% due to possible variations in the thickness of the vessel.The uncertainties on the adjusted values of the three quandties should therefore be increased to 18% at the outer surface of the vessel. (The addidonal unceruinty will

- not affect the values at T/4, T/2, and 3T/4 since these are measured from the inner surface of the vesselin units of the nominal thickness.)

The best estimate values of $>0.1MeV, $>1.0MeV, and the dpa rates at the core mid-height are given in Tables 18 to 38 for the azimuchal variations at the five positions through the vessel. Dese are presented for each of the seven time periods for which calculations were performed,i.e. cycles 1-4, cycle 5, cycles 6&7, cycle 8, cycle 9, cycle 10, and cycle 11.They are the results of the MCBEND calculadons multiplied by the mean adjustment factors de:ived above for the surveillance capsules.

The integrated fluences for cycles 1-11 are summarised in Tables 39 to 41. Rese have j been derived wiA results from Tables 18 to 38 together with the power history of Table '

9 for cycles 1 to 10 and a value of 430 EFPD for cycle 11 taken from reference 8.

It is recommended that for assessing the dose to the vessel the adjusted values of the fluences as given in Tables 18 to 41 should be adopted. For Ge surveillance capsules it is recommended that the adjusted fluences as given in the last three rows of Table 12 should be used when deriving the neutron dose to specimens.

The fluxes at the weld at 450mm below the core centre plane are calculated to be identical to those at the centm plane of the core to within 2% to 3%.

I1 AEAT-0121

REFERENCES ,

1 MCBEND User Guide for Version 9A ANSWERS /MCBEND(94)15 -

2 Dean C J and Eaton C R. 'The 1994 DICE Nuclear Data Librar/*

AEA-RS 5697 -

l 3 Avery A F, Chucas S J, Locke H F and Newbon S. " Calculations of Pressure Vessel Fluence in PWRs Using ENDF/B-VI Data" Proceedings of the 8th .

Intemational Conference on Radiation Shielding" 1994 pp 667 to 685 4 Iztter from Ross D. Snuggerud, Consumers Power,. to Steve Chucas, AEA  ;

Technology., dated 15 January 1995 together with drawings and a diskette contammg pin powers.

5 I.euer from Ross D. Snuggerud, Consumers Power, to Steve Chucas AEA Technology, dated 30 November 1994 together with plant details and the power ,

history.

6 James M F. " Energy Released in Fission" AEEW- M863 7 Kocherov N P and McLaughlin P K  !

The International Dosimetry File (IRDF-90) l IAEA-NDS-141 Rev 2. October 1993 ,

8 Perock J D and Anderson S L " Reactor Vessel Neutron Fluence Measurement -

Program for Palisades Nuclear Plant - Cycles I through 11" WACAP-14557 9 McCracken A K "Few-Channel Unfolding in Shielding - The SENSAK Code" -

Proceedings of Third ASTM-EURATOM Symposium on Reactor Dosimetry 1979 pp732-742 10 Newbon S 'The Analysis of NESDIP 2 with ENDB-B/VI Nuclear Data AEA RS 5591 11 R D Snuggerud, Consumers Power, message to A F Avery, AEA Technology on 17 January 1996.

12 R D Snuggerud, Consumers Power, message to A F Avery, AEA Technology on 7 March 1996.

I 12 AEAT-0121

m Tabla 1 Types cf Fuel Elements per Cycle l .

Number of fuel pins per fuel assembly 208 pins 212 pins 216 pins 208 pins 152 pins 160 pins 202 pins l Cycle +8Rf 4 rows of 2 rows of Steelpins l

~

rods steel rods steel rods at corners one side on 2 sides ,

i 1

1 20 184 1 2 68 136 1 l

3 136 68 4 14 60 5 192 12 6 192 12 7 152 52 8 88 100 16 9 56 132 16 l 10 16 180 16 8 11 16 180 8 16 l I l

I O

l

. 13 AEAT-0121 l

i

3 Table 2 Material Ccmp:sitions a Number Material , Density Composition Fraction  !

(g/cc) (by weight unless stated) , ,

1 Stainless steel b.0 Cr 0.19 Ni 0.10 ~

Fe 0.69 Mn 0.02 2 Carbon Steel 7.9 C 0.0025 Mn 0.0134 Si 0.0028 Mo 0.0053 Fe 0.976 3 Insulanon 0.1545 by volume Air 0.9794 Stainless steel 0.0185 Al 0.0021 4 Water, Core 0.754 by atoms H 0.66667 0 0.33333 5 Conemte 2.45 H 0.004 Fe 0.005 i At 0.003 -

Ca 0.218 Si 0.013 0 0.529 Mg 0.120 -

1 C 0.108 Uramum by atoms U235 0.01715 U238 0.98285 Fuel, UO2 10.2 by atoms U 0.33333 0 0.66667 Zircaloy-4 6.55 Zr U.9824 Sn 0.0145 Fe 0.0021 Cr 0.0010 7

I4 AEAT-0121

i Table 2 Material Ccmpesiticas (centinued) d, j Number Material Density Composition Fraction (g/cc) (by wei;;ht unless j stated)

J

! 6 Fuelelement smear 4.286 zircaloy 0.2058 (208 pins) fuel 0.6997 water 0.09459 7 Fuelelement smear 4.406 zircaloy 0.2035

(216 pins) fuel 0.7068 water 0.08969 3 8 Pm smear over one pitch by volume fuel 0.31877 l

zircaloy 0.11892 water 0.54782

1 void 0.01449

! 9 Guide rod smear over piten 3.8612 by volume zircaloy 0.537057 water 0.462944 10 Air 8.65E-4 N 0.765 0 0.235 11 Low density steel 3.e777 Stamiess steel 1.0 12 Water, downcomer 0.767 by atoms

- H 0.66667 0 0.33333 13 Guide tube smear over pitch 1.4221 by volume

. zimaloy 0.118920 water 0.881080 14 Water, shroud / core banti O.754 by atoms H 0.66667 0 0.33333 ~

15 Cycle 9 only 5.91025 by volume Hf rod / guide tube smear Hf 0.197780 Void 0.016937 Zr 0.190384 Water 0.594899 4

15 AEAT-0121

\

Tcble 3 Tctri S:urces used in the Calculations Cycle Inner

• Outer t Total Source Fuel Elements FuelElements (n/s) .

(n/s) (n/s)

I to 4 3.645E+19 1.204E+19 4.849E+19 5 3.652E+19 1.333E+19 4.985E+19 6 to 7 3.638E+19 1.325E+19 4.963E+19 8 time 1 4.019E+19 9.214E+18 4.940E+19 8 time 2 3.978E+19 1.012E+19 4.990E+19 8 time 3 3.997E+19 1.054E+19 5.051E+19 9 4.244E+19 7.503E+18 4.994E+19 10 4.235E+19 7.454E+18 4.980E+19 11 4.390E+19 5.939E+18 4.984E+19

• Inner fuelelements are:

1, 2, 3, 4, 5, 6, 7, 9, 10, 11, 12, 13, 14, 15, 17, 18, 19, 20, 21, 22, 25, 16, 27, 28, .

29,30,32,33,34,35,39,40,41,42,44,45 .

t Outer fuelelements am:

8, 16, 23,24, 31, 36, 37, 38, 43, 46, 47, 48, 49, 50, 51 .

The fuel element numbers are as shown in figure 3 l

e l

l 16 AEAT-0121

\

l l

i Table 4 30 Energy Group Scheme I

Group Upper Energy Group Upper Energy (mew (mew 1 20.0 16 1.840E-1 2 15.0 17 6.760E 2 i

3 13.5 18 2.480E-2 1 4 12.0 19 9.120E-3 1 5 10.0 20 3.450E-3 1 6 7.790 21 1.235E-3 7 6.070 22 4.540E-4 I 8 3.680 23 1.670E-4 9 2.865 24 6.140E-5 10 2.232 25 2.260E-5 11 1.738 26 8.320E-6 12 1.353 27 3.060E-6 13 0.823 28 1.130E-6 14 0.500 29 4.140E-7 l 15 0.303 30 1.520E 7 0.184 1.000E-7 l l

l l l 5

I 1

17 AEAT-0121

q l

Table 5 Data for the Detector Foils -

l Foil Weight Ah= t- Product Fission Yicid Cycles afterwbich l' Reaction Masenal Fraction of ofTarget Half-life the Foil was Target Isotope in removed from the Element the Plant in the Material Element Copper 1.0 0.6917 5.26 years 5,8,9,10 Cu63(n.a)Co60 Titanium 1.0 0.0825 83.8 days 5,8,9,10 .

T146(n.p)Sc46 Iron 1.0 0.0585 312 days 5,8,9,10 pe54(n.p)Mn54 1.0 0.6777 70.8 days 5,8,9,10 g;58(n.p)CoS8 Nickel Uranium 1.0 1.0 30.2 years 0.06000 5 in Capsule U238(n.f)Cs137 M9 in the Cavity 1.0 1.0 64.2 days 0.65105 5 in Capsule U238(n,f)2r95 Uranium 8 & 9 in the Cavity 1.0 1.0 39.4 days 0.0b29 5 in Capsule U238(n,ORul03 Uranium 8 & 9 in the Cavity 30.2 years 0.06000 9,10 in Capsule U238(n,0Cs137 U"O2 0.848 1.0 0.848 1.0 64.2 days 0.05105 9,10 in Capsule U238(n.OZr95 U"O:

1.0 39.4 days 0.06229 9,10 in Capsule U238(n.ORul03 U"O: 0.S48 1.0 1.0 30.2 years 0.06311 8 & 9 in Cavity Np237(n.OCs137 Neptunium ,

1.0 1.0 64.2 days 0.05941 8 & 9 in Cavity Np237(n.0Zr95 Neptunium 1.0 1.0 39.4 days 0.05380 8 & 9 in Cavity l Np237(n.ORul03 Neptunium ,

l 30.2 years 0.06311 9 in Capsule yp237(n.DCs137 Np*O: 0.881 1.0 64.2 days 0.05941 9 in Capsule sp237(n.0Zr95 Np*O: 0.881 1.0 0.05380 9 in Capsule Np237(n,0Rul03 Np*0 2 0.881 1.0 39.4 days i

Co/Al 0.0102 1.0 5.26 years 8&9 CoS9(n.a)Co60 a!!ov I8 AEAT-0121

Table 6 Measured Decay Rates Cycle Capsule Cu(n.a) Ti(n.p) Fe(n.p) Ni(n.p) U"(n.0 Np*(n.0 5 W 290 Monitors  % 1762 84-1758 84 1759 84-1761 20' 84 1763

. In vessel 84-1764A 84-1765 84 1766 84-1767 D/R dps/a 3.63E 17 9.85E 17 2.80E-15 435E 16 2.68E 15 8 B Monitors 90 1860 90-1861 90-1858 90 1859 Cavity 16' D/R dps/a 1.13E-19 433E 18 2.68E 17 2.87E 17 7.86E 18 1.53E 16 D Monitors 90 1886 90 1874 90-1871 90-1872 Cavity 26' D/R dps/a 8.70E-20 331E 18 2.00E-17 2.15E 17 5.77E 18 1.14E 16 G Monitors 90 1899 90-1900 90 1897 90-1898 Cavity 39' D/R dps/a 6.41E-20 235E 18 1.44E-17 1.53E-17 4.40E-18 8.13E 17 9 1A4F Monitors 92 1146 92-1141 92 1142 92-1145

- In Vssi 20' D/R dps/a 5.89E 18 6.60E 16 1.97E-15 3.91E 15 2.75E 16 J Monitors 92 761 92-762 92-759 92-760 Cavity 16' D/R dps/a 7.06E 20 6.85E 18 2.22E-17 4.96E 17 4.42E 18 731E 17 K Monitors 92 774 92-775 92 772 92 773 Cavity 26' D/R dps/a 6.06E 20 5.79E-18 1.36E 17 4.19E-17 432E 18 6.92E 17 N Monitors92-800 92-801 92 798 92 799 Cavity 39' D/R dps/a 4.19E 20 3.94E-18 1.26E 17 2.68E 17 2.56E 18 4.10E 17 S/9 A Monitors 92 722 92 723 92-720 92-721 Cavity 6' D/R dps/a 1.46E 19 637E 18 2.83E 17 4.51E 17 9.90E 18 1.78E-16 10 W 110 Monitors 93-4210 93 4 205 93-4206 93 4 209 20' 93-4211 In vessel 93-4212 93 4213

' '~~

93 4214 D/R dps/a 3.92E 17 1.88E 16 2.22E-15 1.01E-15 Decay Rates are those at 27 June 1984 for dostmetry removed aner Cycle 5 12 December 1990 for dosimetry removed after Cycle 8 4 March 1992 for dosimetry removed after Cycle 9 12 October 1993 for dosimetry removed after Cycle 10.

The fission rates for the U2 " and Np: foils are derived from the mean values presented in reference 9 using the Cs"' half-life.

19 AEAT-0121

Table 7 Positi:ns cf the Cavity Dosimstry l

Capsule Angle Radial Position A 6 degrees 2558 mm BJ 16 degrees 2581 mm D, K 26 degrees 2604 mm ,

G, N  ; 29 degrees 2675 mm

'Ihe angle is measured relative to the O' axis shown in Figure 2.

The radial position is relative to the axis of the mactor, Table 8 Results for the Surveillance Capsules at 20' Flux or Cycle 5 Cycle 9 Cycle 10 Reaction Calculmed Measured C/M Calculated Mensured C/M Calculated Mensued C/M

$>0.1MeV 1.31E11 7.05E10 5.10E10 2

(n/cm .s)

$>1.0MeV 6.67E10 3.83E10 2.72E10 -

2 (n/cm .s) dpois 9.7E-11 5.52E 11 3.93E-11 Activations at the time of measurement (dps/a)

Cu63(n.a)Co60 3.14E 17 3.63E 17 0.86 5.62E 18 5.89E 18 0.95 3.46E 17 3.92E 17 0.88 7;46(n,p;3,46 1.00E 16 9.85E 17 1.02 6.35E 16 6.60E 16 0.96 1.84E 16 1.88E 16 0.98 p.54(n.pjMn54 2.98E 15 2.80E 15 1.06 2.33E-15 1.97E 15 1.21 2.45E 15 2 "F 15 1.10 Ni38(n.p)CoS8 4.63E 16 4.35E-16 1.06 4.71E 15 3.91E 15 1.21 1.11E 15 1.01E 15 1.10 U:38(n.f)Cs137 3.04E 15 2.68E 15 1.13 3.23E 16 2.75E 16 1.17 4.66E-15 l

i 20 AEAT-0121

Table 9 Power History Cycle Year Month Days Mean Cycle Year Month Days Mean Power Power 1 1971 12 31 0.0003 12 20 0.4427 1972 1 31 0.0827 12 11 0.0000 2 29 0.0095 1976 1 31 0.0000 3 31 0.1314 2 29 0.0000

. 4 30 0.2855 3 31 0.0000 5 31 0.0000 4 30 0.0000 l 6 30 0.3759 5 8 0.0000 7 31 0.3557 2 5 23 0.4076 8 31 0.4211 6- 30 0.8348 9 30 0.2693 7 31 0.5591 10 31 0.3884 8 31 0.6695 11 30 0.3031 9 30 0.7956 12 31 0.5692 10 31 0.6414 1973 1 31 0.3547 11 30 0.5931 2 28 0.0000 12 31 0.8137 3 31 0.5628 1977 1 31 0.7578 4 30 0.8508 2 28 0.8404 5 31 0.5222 3 31 0.8007 6 30 0.8664 4 30 0.7987 7 31 0.8151 5 31 0.5444 8 31 0.2529 6 30 0.8762 9 30 0.0000 7 31 0.8259 10 31 0.0000 8 31 0.5965 11 30 0.0000 9 30 0.7858 12 31 0.0000 10 31 0.8661 1974 1 31 0.0000 11 30 0.8003 2 28 0.0000 12 31 0.9051 3 31 0.0000 1978 1 31 0.1436 4 30 0.0000 1 25 0.0000 5 31 0.0000 2 28 0.0000 6 30 0.0000 3 31 0.0000 7 31 0.0000 4 19 0.0000 8 31 0.0000 3 4 11 0.5713 9 30 0.0000 5 31 0.5033 10 31 0.2056 6 30 0.6836 11 30 0.0046 7 31 0.6844 12 31 0.0000 8 31 0.5573 1975 1 31 0.0000 8 9 30 0.3052 2 28 0.0000 10 31 0.6229 3 31 0.0000 11 30 0.9240

. .- 4 30 0.5313 12 31 0.4511 5 31 0.7090 1979 1 31 0.9571 6 30 0.4794 2 28 0.9440 7 31 0.5930 3 31 0.9485 8 31 0.3981 4 30 0.7527 9 30 0.5368 5 31 0.3138 10 31 0.6031 6 30 0.7122 11 30 0.6659 7 31 0.9046 Note. The mean power is expressed as a fraction of 2530MW.

21 AEAT-0121

Tcbie 9 Power History Continued Cycle Year Month Days Mean Cyde Year Month Days Mean Power Power 8 31 0.8344 4 30 0.9408 -

9 8 0.6636 5 31 0.8969 9 22 0.0000 6 30 0.9671 10 31 0.0000 7 31 0.9221 11 30 0.0000 8 12 0.7462 .-

12 31 0.0000 8 19 0.0000 1980 1 31 0.0000 9 30 0.0000 2 29 0.0000 10 31 0.0000 3 31 0.0000 11 30 0.0000 4 30 0.0000 12 31 0.0000 5 26 0.0000 1984 1 31 0.0000 4 5 5 0.5306 2 29 0.0000 6 30 0.8785 3 31 0.0000 7 31 0.6284 4 30 0.0000 8 31 0.7095 5 31 0.0000 9 30 0.7294 6 30 0.0000 10 31 0.8835 7 30 0.0000 11 30 0.0000 6 7 1 0.1617 12 31 0.4892 8 31 0.0886 1981 1 31 0.9445 9 30 0.1223 2 28 0.9906 10 31 0.0000 3 31 0.9919 11 30 0.2663 .

4 30 0.9608 12 31 0.9766 5 31 0.8720 1985 1 31 0.9576 i 6 30 0.8408 2 28 0.9190 ~

7 31 0.3211 3 31 0.9794 i 8 31 0.4493 4 30 0.8908 5 31 0.9782 i 8 2 0.0000 9 30 0.0000 6 30 0.9377 10 31 0.0000 7 31 0.9687 11 30 0.0000 8 31 0.3405 12 30 0.0000 9 30 0.7537 l 5 12 1 0.0182 10 31 0.8273 i 1982 1 31 0.5036 11 30 0.9575 i 0.0000  !

2 28 0.0990 12 31 3 31 0.3624 1986 1 31 0.0000 4 , 30 0.0000 2 28 0.0000 5  ? 31 0.1925 3 3 0.0000 6 30 0.8862 7 3 28 0.1949 7 31 0.3090 4 30 0.7257 -

. _ . . 8 31 0.0000 5 31 0.5883 9 30 0.8558 6 30 0.0000 10 31 0.8870 '

7 31 0.0000 11 30 0.9896 8 31 0.0000 -

12 31 0.9783 9 -30 0.0000 1983 1 31 0.9257 10 31 0.0000 2 28 0.9853 11 30 0.0000 3 31 0.9895 12 31 0.0000 j

Note. Im mean power is expressed as a fraction of 2530MW.

I 22 AEAT-0121 l

. Table 9 Power History Continued Cycle Year Month Days Mean Cycle Year Month Days Mean  :

Power Power  !

1987 1 31 0.0000 10 31 0.0000 2 28 0.0000 11 30 0.0000 3 31 0.0000 12 31 0.0000 -

4 30 0.5222 1991 1 ?1 0.0000  :

5 31 0.7725 2 28 0.0000  :

6 30 0.7617 3 1 14 0.0000 7 31 0.4650 9 3 17 U.4654 8 31 0.7493 4 30 0.9932 9 30 0.8600 5 31 1.0017 10 31 0.0079 6 30 0.9984 11 30 0.5315 7 31 0.6074 12 31 0.1047 8 31 0.9762 1988 1 31 0.1087 9 30 0.9986 2 29 0.8433 10 31 1.0001 3 31 0.9979 11 30 0.9402 4 30 0.8357 12 31 0.8040 5 31 0.9198 1992 1 31 0.9920 6 30 0.9984 2 7 0.8420 7 31 0.9532 2 22 0.0000 8 31 0.2363 3 31 0.0000 8 22 0.0000 4 18 0.0000 '

. 9 30 0.0000 10 4 12 0.8511 10 31 0.0000 5 31 0.9979 11 28 0.0000 6 30 0.9985

. 8 11 2 0.2441 7 31 0.7398 12 31 0.2414 8 31 0.7753 1989 1 31 0.8808 9 30 0.6921 2 28 0.0000 10 31 0.9452 3 31 0.6631 11 30 0.7280 4 30 0.7642 12 31 0.9990 5 31 0.7967 1993 1 31 0.9985 6 30 0.8002 2 28 0.9990 7 31 0.8027 3 31 0.9991 8 31 0.7129 4 30 0.9272 9 30 0.7978 5 31 0.4583 10 31 0.0003 6 5 0.7835 11 30 0.0000 6 26 0.0000 12 31 0.2668 7 31 0.0000 1990 1 31 0.7293 8 31 0.0000 2 28 0.7954 9 30 0.0000

~3

^~

31 0.7326 10 12 0.0000 4 30 0.4068 5 31 0.2849 6 30 0.5753 7 31 0.7977 8 31 0.7979 9 15 0.7731 9 15 0.0000 Note. The mean power is expressed as a fraction of 2530MW.

23 AEAT-0121

~

Tchte 10 Calculat:d Spectral Resp:nse of the Monitors in the 20' Capsules Group 2 3 4 5 6 7 8 9 10 11 12 Det Cycle Lower Energy Lirait (MeV) 13.5 12.0 10.0 7.79 6.07 3.68 2.87 2.23 1.74 1.35 0.82 Percentage Contribution to the Reaction Rate Cu 5 1.8 2.6 8.9 27.7 38.4 20.3 0.3 0.0 0.0 0.0 0.0 9 0.4 1.6 10.9 31.6 36.0 19.2 0.2 0.0 0.0 0.0 0.0 10 0.0 4.5 6.5 31.0 35.8 21.8 0.2 0.0 0.0 0.0 0.0

'Il 5 0.6 0.9 3.7 15.4 32.6 44.9 1.7 0.0 0.0 0.0 0.0 9 0.2 0.6 4.7 18.4 32.3 42.2 1.6 0.0 0.0 0.0 0.0 10 0.0 1.5 2.6 17.1 31.0 46.3 1.5 0.0 0.0 0.0 0.0 Fe 5 0.1 0.3 1.2 5.8 17.3 48.9 14.3 9.0 2.6 0.4 0.1 9 0.0 0.2 1.6 7.2 18.0 46.8 13.8 9.3 2.6 0.4 0.1 10 0.0 0.4 0.8 6.6 17.4 51.8 12.5 7.5 2.5 0.4 0.1 Ni 5 0.1 0.2 1.1 5.8 16.9 45.1 13.7 11.0 3.8 1.6 0.6 9 0.0 0.1 1.5 7.1 17.5 43.0 13.3 11.3 3.9 1.5 0.7 ,

10 0.0 0.4 0.8 6.6 17.0 48.0 12.0 9.2 3.7 1.5 0.6 Un 2 5 0.2 0.2 0.7 3.5 9.1 22.4 12.2 19.8 17.2 12.8 2.0 .

9 0.0 0.1 1.0 4.4 9.3 21.2 11.7 20.4 17.9 11.9 2.1 10 0.0 0.3 0.5 4.2 9.2 24.9 11.1 17.4 18.2 12.1 2.0 9

24 AEAT-0121

Table 11 Fluxes and D:cty Rates in the Cepsules after Adjustments Initial Std Measured Std Initial Sta Adjusted Std C/M Adj Quantity Calculatd Dev Value Dev C/M Dev Calculatd Dev After Factor Value S  %  % Value  % Adjustment Cvele 5 8

$>0.1MeV(n/cm .s) 1.31 E+ 11 10.1 1.22E+11 7.2 0.93

- 8

$>1.0McV(n/ cm .s) 6.67 E+10 10.1 6.07 E+10 7.2 0.91 dpals 9.70E-11 10.1 9.03E 11 5.5 0.93 Cu(n.p) Decay- 3.14 E- 17 10.7 3.63 E- 17 5 0.86 11.8 3.41E-17 7.7 0.94 1.09 Rate (dps/a)-

TI(n.p) Decay - 1.00E 16 10.4 9.85 E- 17 5 1.02 11.5 9.83E 17 7.4 1.03 0.98 Rate (dpsis) -

Fe(n.p) Decay - 2.98E 15 10.1 2.80E 15 5 1.06 11.3 2.81 E-15 7.3 1.00 0.94

,_ Rate (dps/a) l Ni(n.p) Decay - 4.63E 16 10.1 4.35E 16 5 1.06 11.3 4.5 2E- 16 7.3 1.00 0.98 Rate (dps/a)

U8"(n.f) Decay - 3.04E-15 9.9 2.68E 15 5 1.13 11.1 2.77E-li 7.4 1.03 0.91 Rate (dos /a)

Cvele 9 l

8

$>0.!MeV(n/cm .s) 7.05 E+10 10.2 6.37 E+10 10.0 0.90 i

8

$>1.0MeV(n/cm .s) 3.83 E+ 10 10.2 3.27 E+ 10 9.9 0.85 dp:/s 5.52E 11 10.0 4.73E-11 7.5 0.86 Cu(n.p) Decay - 5.62E-18 10.5 5 89E-18 5 0.95 11.6 5.82E 18 10.7 0.98 1.04

. Rate (dps/a)

Ti(n.p) Decay - 6.35E 16 10.3 6.60E-16 5 0.96 11.4 6.13E 16 10.4 0.93 0.97 Rate (dps/s)

Fe(n.p) Decay - 2.38 E- 15 10.0 1.97 E- 15 5 1.21 11.2 2.06E-15 10.5 1.05 0.87 Rate (dps/a)

Ni(n.p) Decay - 4.71 E- 15 10.0 3.91 E- 15 5 1.21 11.2 4.08E 15 10.2 1.05 0.87 Rate (dps/a)

U8"(n.f) Decay - 3.23E 16 10.0 2.75 E- 16 5 1.18 11.2 2.76E 16 10.2 1.01 0.85 Rate (dns/a)

Cvele 10 l $>0.1MeV(n/cm .s) 5.10E+10 10.7 8

4.98E+10 8.8 0.98

$>1.0MeV(n/cm .s) 2.72 E+10 10.5 8

2.61 E+ 10 9.2 0.96 l 3.93E 11 10.2 3.75E-11 6.7 0.95 dpal:

Cu(n.p) Decay ,

3.46E 17 10.8 3.92E 17 5 0.88 11.9 3.77E 17 8.0 0.96 1.09 Rate (dps/a)

Ti(n.p) Decay - 1.84E 16 10.1 1.88E 16 5 0.98 11.3 1.86E 16 7.7 0.99 1.01 Rate (dps/a)

Fe(n.p) Decay - 2.45E 15 10.1 2.22E 15 5 1.1 11.3 2.29E 15 7.6 1.03 0.93 i Rate (dps/a)

Ni(n.p) Decay - 1.11E-15 10.1 1.01E 15 5 1.1 11.3 1.04E 15 7.4 1.03 0.94 Rate (dps/a)

U8"(n.f) Decay - 4.66E-15 10.1 Rate (dps/a) i

! 25 AEAT-0121 1 .

-. - - -_- _~ .-. . - - - -. -. - - - - - -

Table 12 Calculat:d Reaction Rates and Fluxes for the 20' Capsules l

Quantity Cycles

14 5 6&7 8 9 10 11 Cu(n.a) (dps) 8.49E 17 9.90E-17 9.97E 17 8.00E-17 5.57E-17 4.07E-17 3.61E 17 -

l Ti(n.p)) (dps) 1.40E 15 1.60E-15 1.57E 15 130E 15 9.16E 16 6.60E 16 5.79E 16 f Fe(n.p)) (dps) 8.23E 15 9.15E 15 8.78E-15 7.50E 15 533E 15 3.79E 15 3.25E 15 ,

i Ni(n.p) ) (dps) 1.07E 14 1.19E 14 1.14E-14 9.76E 15 6.88E-15 4.91E-15 4.19E-15 U"(n.O ) (dps) 2.87E 14 2.99E 14 2.91E 14 2.50E 14 1.74E 14 1.25E 14 1.03E 14 2

f>0.1MeV (n/cm .s) 1.21E11 131E11 1.23E11 1.04E11 7.05E10 5.10E10 4.24E10 2

f>1.0Mev (n/cm .s) 6.45E10 6.67E10 636E10 5.51E10 3.83E10 2.72E10 2.21E10 Dpa rate (dpa/s) 9.12E 11 9.70E 11 9.01E 11 7.%E-11 5.52E 11 3.93E-11 3.25E 11 i

EFPS (secs) 130E08 3.41E7 6.07E7 3.23E7 2.58E7 3.08E7 3.72E7 Elura;ti Fluence E>0.1 MeV 1.57E19 4.47E18 7.47E18 336E18 1.82E18 1.57E18 1.58E18 2

(n/cm )

Fluence E>1.0MeV 839E18 2.28E18 3.86E18 1.78E18 9.89E17 839E17 8.22E17 2

(n/cm ) .

I dpa 1.19E-2 331E 3 5.47E-3 2.57E-3 1.43E 3 1.21E-3 1.21E 3 cmnnheive winr<

Fluence E>0.1 MeV 1.57E19 2.02E19 2.77E19 3.10E19 3.29E19 3.44E19 3.60E19 1 2

(n/cm ) l Fluence E>1.0MeV 839E18 1.07E19 1.45E19 1.63E19 1.73E19 1.81E19 1.90E19 i (n/an')

(dpa) 1.19E 2 1.52E-2 2.06E 2 232E 2 2.46E 2 2.59E 2 2.71E 2 AWer-! rumnkrive Whm Fluence E>0.1 MeV 1.48E19 1.90E19 2.60E19 2.92E19 3.09E19 3.24E19 3.49E19 (n/cm:)

Fluer.ce E>1.0MeV 7.64E18 9.71E18 132E19 1.48E19 1.57E19 1.65E19 1.73E19 2

(n/cm )

(dpa) 1.08E 2 138E 2 1.88E-2 2.11E 2 2.24E 2 235E-2 2.46E 2

~

Note: The adjusted values have been multiplied by mean factors for the three capsules; ,

i.e. 0.94 for $>0.1MeV, and 0.91 for $>l.0MeV and dpa. I 26 AEAT-0121

Table 13 Calculated Axial Diaributions of Fluences in the 20' Capsules Distance from Fluences Cycles 1 to 11 Core Centre dpa

$>0.1MeV $>1.0MeV Plane (cm) n/cm2 n/cm2 125 to 175 1.82E+19 9.61E+18 1.39E-02 75 to 125 3.17E+19 1.72E+19 2.44E.02 25 to 75 3.48E+19 1.88E+19 2.64E-02 l -25 to 25 3.60E+19 1.90E+19 2.71E-02

-75 to -25 3.55E+19 1.91E+19 2.71E-02

-125 to -75 3.31E+19 1.78E+19 2.55E , -175 to -125 1.91E+19 1.01E+19 1.44E-02 Table 14 Calculated Fluxes and Decay Rates in the Cavity Cycle ,>0.1Mov ,>t.0Mey Cu(n.p) Ti(n.p) Fe(n.p) Ni(n.p) U238(n.f) Np237(n.f) l l

. Angle 16* 1.23E10 1.46F.9 1.14 E.19 4.56E.18 3.11E.17 3.25E.17 9.87E.18 1.51E.16 SW Dv 1.0 2.0 3.5 2.6 1.9 1.7 1.9 1.2 8 Angle 26' 1.09E10 1.09E9 1.01 E.19 3.71E.18 2.46E.17 2.60E.17 7.71E.18 1.21E.16 SW Dv 1.2 2.2 3.3 2.7 2.0 1.8 2.0 1.4 Angle 39' 7.23E9 6.97E8 6.41E.20 2.27 E.18 1.45E.17 1.55E.17 4.66E tB 7.62E.17 SW Dv 1.3 3.1 3.8 3.0 2.5 2.4 3.5 1.7 Angle 16' 9.05E9 1.0$E9 8.15 E.20 8.11 E.18 2.86E.17 6.14 17 5.97E.18 9.11E.17 SW Dv 1.1 2.0 4.1 3.5 2.4 2.1 1.9 1.2 9 Angle 26' 8.34E9 9.12E8 6.75 E.20 6.67E.18 2.44E.17 5.24E.17 5.07E.18 7.88E.17 SW Dv 1.7 2.3 4.1 3.6 2.7 2.5 2.1 1.7 Angle 39' 5.98E9 5.97E8 4.29E 20 4.09 E.18 1.49E.17 2.87E.17 3.26E.18 5.37E.17 1.5 3.0 4.1 3.1 3.2 2.9 2.4 1.8 SW Dv - -

6' 1.65 E.19 7.50E.18 3.64E.17 5.78E.17 1.44E.17 2.16E.16 M9 Angle 4.87E9 5.67EB 2.3 7.7 3.0 1.7 2.0 1.7 1.0 SW Dv 1.2

' Note. 'Ihe standard deviadons are those arising solely from the Monte Carlo statisdes and they are expressed as percents.ges.

'Ihe decay rates for the detectors are the calculated values at 12 December 1990 and i

4 March 1992 for dosimetry removed after cycles 8 and 9 respectively.

27 AEAT-0121

Table 15 Vdues cf C/M in the Cevity .

Angle 6' '

Cycles Reaction Cycle 16' 26' 39' 8+9 ,

Cu(n.a) Cycle 8 1.01 1.16 1.00 1.15 Cycle 9 1.15 1.11 1.02 Ti(n.p) Cycle 8 1.05 1.12 0.96 1.18 Cycle 9 1.18 1.15 1.04 Fe(n.p) Cycle 8 1.17 1.23 1.01 1.30 Cycle 9 1.29 1.29 1.18 N1(n.p) Cycle 8 1.13 1.21 1.01 1.28 Cycle 9 1.24 1.25 1.13  !

U238(n,f) Cycle 8 1.25 1.34 1.06 1.65 Cycle 9 1.35 1.17 1.27 Np237(n,f) Cycle 8 0.98 1.06 0.94 1.35 Cycle 9 1.25 1.14 1.31 1

O L

im s m e e

28 AEAT-0121

Table 16 Criculated Sptctral Rtsponse cf the Mcnit:rs in the Cavity for Cycle 8 Group 3 l4 l5 l6 l7 l8 l 9 l 10 l 11 l 12 l 13 l 14 l 15 l 16 l 17 30 Det Angle Lower Energy Limit (MeV) 12.0 l 10.0 l 7.79 l 607 l 3.68 l 187 l 2.23 l 1.74 l 1.35 l a82 l 0J0 l 0.30 l a18 l a068 l 0.0 Percentage Contribution to the Reacuon Rate Cu 16' 5.5 12.2 34.8 31.6 15.6 0.2 26' 17 13.2 384 30J 14.6 0.3 39' 5.8 12.5 34.9 32.1 14.1 0.2 13 16' 12 5.8 22.1 30.8 37 4 1.4 26' l.1 65 24.0 30.0 36.5 1.8 39' 14 64 23.4 31.8 34.1 1.8 Fe 16' OL7 10 8.9 17J 40.8 13.2 10.7 4.6 1.2 0.6 26' OL2 2.2 9.2 16.8 40.1 13.9 11.0 4.9 1.1 a6 39' 47 13 9.6 18.0 38.4 14.6 10.1 4.6 1.1 0.5 I Ni 16' O.6 1.8 8.2 15.7 34.7 11.8 11.2 6J 4.1 3J 1.0 26' O.2 10 8.5 15.2 34.2 12.5 12J 6.7 3.7 3J 1.0 39' O.6 2.1 8.9 1&4 32.7 13.2 11J 6.4 3.9 3.3 1.0 U" 16' O.3 a8 3.6 61  !!.8 7.6 16.0 21.9 23.0 7J as al 26' O.2 0.9 3.8 5.8 12.2 7.8 16.6 23.1 20.7 7.6 0.9 0.1 39' O.4 a9 4.0 &5  !!J L3 15.6 21.5 22.4 7.2 &9 at at 0.1 04 Np* 16' a0 al a6 49 2.2 1.6 3.4 4.8 7.4 27.7 35J L1 12 14 JJ 26* 40 al 46 0.9 2.3 1.6 3J 5.0 L7 27.3 36J L1 2.2 1.6 34

. 39' al at 0.6 0.9 2.0 1.6 3.1 4.4 6.6 25J 3&5 L7 2.7 2.0 5.0

& ee e 4

e 29 AEAT-0121

_ - ~ _ _ _ _ _ _ _ _ _ , .

Table 17 Adjusted Fluxes and C/Ms in the Cavity C dpa Cu(n.p) Ti(n.p) Fe(n.p) Ni(n.p) U(nJ) Np(nJ) y

$>0.1MeV $>1.0MeV c n/cm 8.s n/cm'.s dps/a C/M C/M C/M C/M C/M C/M 1 -

8 Mjustd 1.23 E10 1.33E9 4.25E12 0.99 0.99 1.02 0.99 1.01 0.99 16' Std Dv 7.3 5.0 5.5 4.7 4.6 4.6 4.5 7.5 8.4 -

Initial 1.23E10 1.46E9 4.12E12 1.01 1.05 1.17 1.13 1.25 0.98 Factor 1.00 0.91 0.97 0.98 0.94 0.';. 7 0.88 0.81' l.01 8 Mjused 1.06E10 9.26E8 3.42E12 1.02 0.97 1.02 1.00 1.01 1.00 26' Std Dv 9.1 4.0 6.8 5.6 5.5 5.4 5.3 9.0 9.9 Initial 1.09E10 1.09E9 3.64E12 1.16 1.12 1.23 1.21 1.34 1.06 Factor 0.97 0.85 0.94 0.88 0.87 0.83 0.83 0.75 0.94 8 Mjustd 7.23 E9 6.76E8 2.24E12 1.01 0.98 1.01 1.00 1.00 1.00 39' Sid Dv 4.3 5.9 3.8 2.2 2.2 2.1 2.1 3.5 6.6 Initial 7.23 E9 6.97E8 2.26E12 1.00 0.96 1.01 1.01 1.06 0 94 Factor 1.0 0.96 0.99 1.01 1.02 1.01 0.99 0.94 1.06 9 Mjustd 3.05 E9 8.82E8 2.66E12 1.00 0.99 1.02 0.99 1.01 1.01 16' Std D v 6.1 9.5 7.2 6.0 5.9 5.9 5.7 9.4 11.1 Initial 9.0$E9 1.05E9 3.06E12 1.15 1.18 1.29 1.24 1.35 1.25 -

Factor 0.89 0.84 0.87 0.87 0.84 0.79 0.8,0 . 0.75 0.81 9 Mjused 7.76E9 7.93E8 2.50E12 1.00 0.98 1.03 1.00 1.00 1.00 ,,

26' Std Dv 9.2 4.6 6.9 5.6 5.7 5.6 5.4 8.5 10.4

'mtial 3.34E9 9.12ES 2.72E12 1.11 1.15 1.31 1.25 1.17 1.14 Factor 0.93 0.87 0.92 0.90 0.85 0.79 0.80 0.85 0.88 9 Mjustd 5.28E9 4.66E8 1.70E12 1.00 0.99 1.03 0.98 1.01 1.01 l 39' SulDv 10.2 10.1 7.5 5.6 5.5 5.5 5.4 9.2 11.2 Initial 5.98E9 5.97E8 1.97E12 1.02 1.04 1.18 1.33 1.27 1.31 F2ctor 0.88 0.73 0.87 0.98 0.95 0.87 0.87 0.30 0.77 Note " Adjusted" = values of the parameters after adjustment by SENSAK.

"Std Dv" = percentage standard deviation assigned to the adjusted parameters by SENSAK.

" Initial" = values of the parameters before adjustment

" Facto ( = factor by which the parameter has been changed by SENSAK. .

30 AEAT-0121

1 Table 18 Cycles 1 to 4 Combined, Flux >0.1MeV in Vessel Wall at Mid height  ;

Angle frtsu Dtstance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge 0'to 5' 7.41E+10 6.05E+10 4.38E+10 2.96E+10 1.64E+10 5' to 10* 8.32E+10 6.64E+10 4.86E+10 3.25E+10 1.81E+10 10' to 15' 9.48E+10 7.67E+10 5.50E+10 3.57E+10 1.99E+10 15' to 20' 9.88E+10 7.90E+10 5.55E+10 3.66E+10 2.01E+10 20* to 25' 8.49E+10 6.69E+10 4.91E+10 3.28E+10 1.82E+10 25' to 30' 7.30E+10 6.06E+10 4.44E+10 2.91E+10 1.63E+10 30' to 35' 7.51E+10 - 5.97E+10 4.34E+10 2.87E+10 1.63E+10 35' to 40' 6.47E+10 5.26E+10 3.77E+10 2.53E+10 1.46E+10 40* to 45' 5.04E+10 4.20E+10 3.07E+10 2.14E+10 1.27E+10 45* to 50' 4.93r : 10 4.04E+10 3.11E+10 2.17E+10 1.36E+10 50' to 55' 6.6610 5.23E+10 3.72E+10 2.60E+10 1.53E+10 55' to 60* 7.88E+10 6.22E+10 4.42E+10 2.89E+10 1.67E+10 60* to 65* 7.66E+10 6.24E+10 4.45E+10 3.01E+10 1.71E+10 65* to 70* 8.16E+10 6.91E+10 4.93E+10 3.32E+10 1.85E+10 70* to 75* 9.91E+10 7.81E+10 5.55E+10 3.65E+10 1.99E+10 75* to 80* 9.63E+10 7.55E+10 5.42E+10 3.54E+10 1.97E+10 80* to 85* 8.00E+10 6.58E+10 4.76E+10 3.19E+10 1.84E+10 85* to 90* 7.53E+10 6.14E+10 4.39E+10 2.93E+10 1.68E+10 Table 19 Cycle 5, Flux >0.1MeV in Vessel Wall at Mid height Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to5' 7.96E+10 6.41E+10 4.83E+10 3.21E+10 1.93E+10 5' to 10' 8.80E+10 7.10E+10 5.22E+10 3.49E+10 2.03E+10 10' to 15* 1.04E+11 8.51E+10 6.00E+10 3.89E+10 2.16E+10 15* to 20* 1.11E+11 8.71E+10 6.20E+10 4.05E+10 2.24E+10 20* to 25' 9.50E+10 7.66E+10 5.53E+10 3.69E+10 2.09E+10 25* to 30' 8.63E+10 6.89E+10 4.95E+10 3.34E+10 1.93E+10 30* to 35' 8.58E+10 6.85E+10 4.88E+10 3.24E+10 1.89E+10 35' to 40' 7.33E+10 6.08E+10 4.39E+10 2.93E+10 1.70E+10 40' to 45* 5.47E+10 4.62E+10 3.43E+10 2.43E+10 1.48E+10 i 45* to 50* 5.52E+10 4.71E+10 3.46E+10 2.46E+10 1.54E+10 l 50' to 55' 7.47E+10 6.01E+10 4.34E+10 2.93E+10 1.67E+10

. 55' to 60* - -8:57E+10 6.84E+10 4.92E+10 3.35E+10 1.90E+10 60* to 65* 8.84E+10 7.29E+10 5.26E+10 3.50E+10 2.01E+10 65* to 70* 9.86E+10 7.92E+10 5.71E+10 3.76E+10 2.10E+10

- 70* to 75* 1.09E+11 8.62E+10 6.10E+10 4.01E+10 2.14E+10 ,

75* to 80* 1.03E+11 8.41E+10 5.90E+10 3.89E+10 2.17E+10 80* to 85* 9.18E+10 7.38E+10 5.38E+10 3.53E+10 1.98E+10 85* to 90* 7.71E+10 6.55E+10 4.67E+10 3.18E+10 1.82E+10

~ _ _ - .__- - . . _ _ _ _ _ . - . _ _ _ _ _ _ _ _ _ . _ . _ . - - _ . ._

-_7

~

Table 20 Cycles 6 and 7 Cembined, Flux >0.1MeV in Vessel Wall at Mid.

height

~

Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O to 5' 8.61E+10 7.02E+10 5.18E+10 3.53E+10 2.02E+10 5' to 10' 8.99E+10 7.42E+10 5.51E+10 3.70E+10 2.08E+10 10' to 15* 1.04E+11 8.21E+10 5.96E+10 3.93E+10 2.18E+10 15' to 20* 1.04E+11 8.24E+10 6.08E+10 3.85E+10 2.10E+10 20* to 25' 9.46E+10 7.88E+10 5.47E+10 3.75E+10 2.03E+10 25* to 30' 8.73E+10 7.18E+10 5.26E+10 3.54E+10 1.98E+10 30* to 35' 8.50E+10 6.82E+10 4.73E+10 3.13E+10 1.83E+10 35' to 40* 7.44E+10 5.80E+10 4.32E+10 2.85E+10 1.64E+10 40' to 45' 5.53E+10 4.62E+10 3.52E+10 2.40E+10 1.48E+10 45' to 50' 5.19E+10 4.65E+10 3.39E+10 2.34E+10 1.45E+10 50' to 55' 7.21E+10 5.90E+10 4.14E+10 2.82E+10 1.67E+10 55* to 60* 8.62E+10 6.88E+10 - 4.90E+10 3.29E+10 1.83E+10 60* to 65* 8.18E+10 6.62E+10 4.78E+10 3.37E+10 1.93E+10 65* to 70* 9.60E+10 7.56E+10 5.26E+10 3.57E+10 2.05E+10 70* to 75* 1.08E+11 8.62E+10 6.01E+10 4.01E+10 2.20E+10 75* to 80* 1.11E+11 8.88E+10 6.32E+10 4.12E+10 2.19E+10 80* to 85* 9.22E+10 7.51E+10 5.44E+10 3.65E+10 2.03E+10 85* to 90* 9.12E+10 6.96E+10 5.11E+10 3.42E+10 1.91E+10 Table 21 Cycle 8, Flux >0.1MeV in Vessel Wall at Mid. height Angle from Distance Through Vessel Wall (T is wall thickness) -

Ve:tical Inner Ecge T/4 T/2 3T/4 Outer Edge 0'to 5' 4.31E+10 3.74E+10 2.82E+10 1.95E+10 1.16E+10 5' to 10' 6.30E+10 4.99E+10 3.64E+10 2.43E+10 1.36E+10 10' to 15* 8.54E+10 6.67E+10 4.74E+10 3.11E+10 1.64E+10 15* to 20' 9.12E+10 7.29E+10 5.06E+10 3.27E+10 1.70E+10 20* to 25' 7.31E+10 5.86E+10 4.13E+10 2.72E+10 1.44E+10 25' to 30' 5.06E+10 4.13E+10 2.93E+10 2.03E-10 1.13E+10 30' to 35* 3.65E+10 3.06E-10 2.25E+10 1.58E-10 9.51E+09 35' to 40' 3.19E+10 2.64E+10 1.94E+10 1.38E+ 10 8.43E+09 i 40' to 45* 2.93E+10 2.39E+10 1.78E+10 1.24E+10 7.81E+09 45' to 50* 2.90E+10 2.39E+10 1.74E+10 1.23E+10 7.86E+09 50* to 55* 3.16E+10 2.59E+10 1.93E+10 1.35E+10 8.38E+09 55' to 60* ,

_3,65E+10 3.04E+10 2.24E+10 1.55E+10 9.57E+09 -

60* to 65* 5.13E+10 4.04E+10 2.96E+10 1.99E+10 1.17E+10 65* to 70* 7.18E+10 5.70E+10 4.11E+10 2.70E+10 1.46E+10  !

70* to 75* 9.26E+10 7.24E+10 5.00E+10 3.21E+10 1.69E+10 -

75* to 80* 8.45E,10 6.775-10 4.6SE+10 3.02E+10 1.60E+10 80* to 85* 5.99E+10 4.95E+10 3.51E+10 2.36E+10 1.30E+10 85* to 90* 4.26E+10 3.66E+10 2.73E+10 1.87E+10 1.12E+10 9

32 AEAT-0121

Table 22 Cycle 9, Flux >0.1MeV in Vessel Wall at Mid-height Angle from Distance Through Vessel Wall (T is wall duckness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge

. O'to 5' 3.98E+10 3.39E+10 2.47E+ 10 1.67E+10 9.78E+09 5* to 10' 4.79E+10 3.73E+10 2.74E+10 1.88E+10 1.05E+10 10* to 15' 5.48E+10 4.47E+10 3.20E+10 2.15E+10 1.15E+10 15' to 20* 6.01E+10 4.68E+10 3.34E+10 2.20E+10 1.15E+10 20* to 25' 5.19E+10 4.07E+10 3.00E+10 1.98E+10 1.11E+10 i 25' to 30' 4.22E+10 3.49E+10 2.49E+10 1.67E+10 9.52E+09 l 30* to 35* 3.55E+10 2.84E+10 2.08E+10 1.41E+10 8.15E+09

! 35* to 40* 2.94E+10 2.38E+10 1.73E+10 1.20E+10 7.37E+09 40* to 45* ' 2.23E+10 1.92E+10 1.41E+10 1.03E+10 6.37E+09 45' to 50* 2.19E+10 1.87E+10 1.38E+10 9.87E+09 6.43E+09

! $0* to 55* 2.74E+10 2.28E+10 1.65E+10 1.15E+10 7.02E+09 l 55* to 60* 3.50E+10 2.86E+10 2.05E+10 1.37E+10 8.10E+09 l 60* to 65* 4.30E+10 3.48E+10 2.44E+10 1.63E+10 9.33E+09 l 65* to 70* 4.99E+10 3.87E+10 2.83E+10 1.93E+10 1.03E+10

70* to 75* 5.80E+10 4.61E+10 3.27E+10 2.14E+10 1.14E+10 75* to 80* 5.54E+10 4.44E+10 3.16E+10 2.08E+10 1.14E+10 l 80* to 85* 4.62E+10 3.80E+10 2.75E+10 1.88E+10 1.07E+10 l 85* to 90* 4.13E+10 3.36E+10 2.49E+10 1.66E+10 9.73E+09 Table 23 Cycle 10, Flux >0.1MeV in Vessel Wall at Mid height Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 3.12E+10 2.55E+10 1.85E+10 1.29E+10 7.86E+09 l 5* to 10' 3.54E+10 2.91E+10 2.12E+10 1.43E+10 8.12E+09 '

10' to 15' 4.32E+10 3.43E+10 2.48E+10 1.63E+10 8.80E+09 15* to 20' 4.52E+10 3.51E+10 2.52E+10 1.67E+10 8.90E+09 20* to 25' 4.11E+10 3.30E+10 2.36E+10 1.56E+10 8.72E+09 l

25* to 30' 3.93E+10 3.16E+10 2.20E+10 1.46E+10 8.22E+09 30* to 35' 3.50E+10 2.84E+10 2.0$E+10 1.36E+10 7.56Et09 35' to 40* 2.91E+10 2.36E+10 1.75E+10 1.19E+10 6.92E+09 40* to 45* 2.37E+10 2.05E+10 1.55E+10 1.07E+10 6.36E+09 45' to 50* 2.58E+10 2.14E+10 1.56E+10 1.08E+10 6.37E+09 50* to 55' 3.00E+10 2.45E+10 1.81E+10 1.22E+10 7.04E+09 55' to 60* 3.49E+10 2.78E+10 2.01E+10 1.31E+10 7.42E+09 60* to 65* - -3.158E+10 3.04E+10 2.12E+10 1.42E+10 8.20E+09 65* to 70* 3.96E+10 3.27E+10 2.38E+10 1.61E+10 8.86E+09 70* to 75* 4.41E410 3.54E+10 2.54E+10 1.64E+10 9.01E+09 75* to 80* 4.20E+10 3.32E+10 2.42E+10 1.58E+10 8.90E+09 80* to 85* 3.52E+10 2.95E+10 2.12'd+10 1.41E+10 7.79E+09 85* to 90* 2.89E+10 2.45E+10 1.80E+10 1.26E+10 7.32E+09 l

33 AEAT-0121

Teble 24 Cycle 11, Flux >0.1MeV in Vessel Wall at Mid height -

Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 2.71E+10 2.19E+10 1.58E+10 1.11E+10 6.40E+09 5' to 10' 3.16E+10 2.51E+10 1.81E+10 1.25E+10 6.91E+09 -

10* to 15' 3.55E+10 2.82E+10 2.00E+10 1.30E+10 7.45E+09 15* to 20' 3.54E+10 2.86E+10 2.05E+10 1.34E+10 7.47E+09 20* to 25* 3.24E+10 2.53E+10 1.88E+10 1.25E+10 7.13E+09 -

25' to 30* 2.89E+10 2.48E+10 1.77E+10 1.18E+10 7.01E+09 30' to 35* 2.82E+10 2.32E+10 1.68E+10 1.09E+10 6.33E+09 35' to 40* 2.28E+10 1.92E+10 1.39E+10 9.54E+09 5.63E+09 40* to 45* 1.93E+10 1.65E+10 1.21E+10 8.67E+09 5.34E+09 45' to 50* 1.99E+10 1.64E+10 1.20E+10 8.54E+09 5.21E+09 50' to 55* 2.50E+10 1.97E+10 1.42E+10 9.60E+09 5.72E+09 55' to 60* 2.84E+10 2.30E+10 1.66E+10 - 1.11E+10 6.47E+09 60* to 65* 3.06E+10 2.43E+10 1.81E+10 1.19E+10 6.91E+09 65* to 70* 3.22E+10 2.74E+10 2.00E+10 1.32E+10 7.42E+09 70* to 75" 4.00E+10 3.13E+10 2.17E+10 1.45E+10 7.86E+09 75* to 80* 4.03E+10 3.27E+10 2.23E+10 1.49E+10 8.11E+09 80* to 85* 3.32E+10 2.72E+10 1.95E+10 1.31E+10 7.46E+09 85* to 90* 2.69E+10 2.21E+10 1.65E+10 1.13E+10 6.71E+09

~

Table 25 Cycles 1 to 4 Combined. Flux >1.0MeV in Vessel Wall at Mid-height Angle trom Distance Tnrough Vessel Wall (T is wall thickness) ,,

' Vertical Inner Edge T/4 T/2 3T/4 Outer Edge 0"to 5' 3.33E+10 1.90E+10 9.72E+09 4.44E+09 1.79E+09 5* to 10' 3.79E+10 2.06E+10 1.05E+10 4.87E+09 2.03E+09 10' to 15* 4.48E+10 2.43E+10 1.22E+10 5.49E+09 2.28E+09 15* to 20* 4.57E+10 2.45E+10 1.15E+10 5.53E+09 2.19E+09 20* to 25* 3.88E+10 2.08E+10 1.0.tE+10 4.82E+09 1.95E+09 25' to 30' 3.26E-10 1.81E+10 8.975-09 4.19E+09 1.78E+09 30' to 35* 3.39E+10 1.87E+10 8.94E-09 4.17E+09 1.78E+09 35' to 40* 2.91E+10 1.61E+10 7.67E+09 3.54E+09 1.50E+09 40' to 45* 2.28E+10 1.29E+10 6.29E+09 3.07E+09 1.32E+09 45' to 50' 2.24E+10 1.22E+10 6.24E+09 2.93E+09 1.31E+09 .

50' to 55* 3.03E+10 - 1.62E+10 7.89E+09 3.78E+09 1.56E+09 l '

55' to 60* 3.57E+10 1.96E+10 9.55E+09 4.39E+09 1.83E+09 '

60* to 65* - -3:62E+10 1.96E+10 9.42E+09 4.21E+09 1.81E+09 65* to 70* 3.74E+10 2.12E+10 1.04E+10 4.93E+09 2.01E+09 70* to 75* 4.58E+10 2.46E+10 1.18E+10 5.41E+09 2.17E+09 ~

75* to 80* 4.40E+10 2.38E+10 1.18E+10 5.54E+09 2.24E+09 80* to 85* 3.66E+10 2.02E+10 9.88E@ 4.67E+09 1.93E+09 85* to 90* 3.49E+10 1.88E+10 9.18E+09 4 36E+09 1.79E+09 34 AEAT-0121

. Table 26 Cycle 5, Flux >1.0MeV in Vessel Wall at Mid-height Angie trum Distance Through Vessel Wall (T is wall duckness)

Vertical Inner Edge- T/4 T/2 3T/4 Outer Edge O'to 5' 3.70E+10 1.94E+10 9.85E+09 4.57E+09 1.93E+09 5* to 10* 3.95E+10 2.17E+10 1.07E+10 4.91E+09 2.06E+09 10' to 15' 4.85E+10 2.61E+10 1.27E+10 5.71E+09 2.36E+09 15' to 20' 5.01E+10 2.70E+10 1.30E+10 6.14E+09 2.52E+09 20* to 25' 4.43E+10 2.38E+10 1.18E+10 5.48E+09 2.32E+09 i 25' to 30* 3,87E+10 2.07E+10 1.03E+10 4.84E+09 2.02E+09 l

30' to 35* 3.90E+10 2.10E+10 1.06E+10 4.84E+09 2.01E+09 35* to 40* 3.36E+10 1.85E+10 9.06E+09 4.14E+09 1.78E+09 40* to 45* 2.51E+10 1.37E+10 7.01E+09 3.29E+09 1.43E+09 45' to 50* 2.54E+10 1.36E+10 7.04E+09 3.33E+09 1.43E+09 l 50* to 55' 3.42E+10 1.84E+10 9.06E+09 4.26E+09 1.80E+09

! 55' to 60* 4.01E+10 2.12E+10 1.04E+10 4.91E+09 1.98E+09

! 60* to 65* 4.04E+10 2.13E+10 1.09E+10 4.94E+09 2.09E+09 l 65* to 70* 4.40E+10 2.39E+10 1.18E+10 5.23E+09 2.20E+09 l 70* to 75* 5.00E+10 2.67E+10 1.28E+10 6.13E+09 2.43E+09 1 75* to 80* 4.70E+10 2.62E+10 1.24E+10 5.91E+09 2.27E+09 i 80* to 85* 4.19E+10 2.29E+10 1.12E+10 4.95E+09 2.26E+09 85* to 90* 3.59E+10 1.99E+10 9.57E+09 4.68E+09 1.91E+09 l

l Table 27 Cycles 6 and 7 Combined, Flux >1.0MeV in Vessel Wall at Mid-height Angle trom Distance Through Vessel Wall (T is wall duckness) l Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O' to 5' 4.02E+10 2.23E+10 1.13E+10 5.13E+09 2.20E+09 5* to 10' 4.43E+10 2.39E+10 1.16E+10 5.55E+09 2.32E+09 10' to 15* 4.96E+10 2.61E+10 1.28E+10 6.07E+09 2.52E+09 15' to 20' 4.86E+10 2.58E+10 1.29E+10 5.64E+09 2.33E+09 20* to 25' 4.31E+10 2.31E+10 1.12E+10 5.09E+09 1.99E+09 25' to 30* 3.88E+10 2.13E+10 1.06E+10 5.26E+09 2.13E+09 30' to 35' 3.90E+10 2.07E+10 1.00E+10 4.59E+09 1.93E+09 35* to 40* 3.42E+10 1.83E+10 9.01E+09 4.13E+09 1.76E+09 40* to 45* 2.40E+10 1.32E+10 6.79E+09 3.11E+09 1.46E+09 45* to 50* 2.39E+10 1.39E+10 6.55E+09 3.22E+09 1.44E+09

. 50* to 55* - -3.19E+10 1.85E+10 8.48E+09 4.04E+09 1.71E+09 55* to 60* 3.94E+10 2.14E+10 1.05E+10 4.91E+09 1.95E+09 60* to 65* 3.93E+10 2.03E+10 9.79E+09 4.91E+09 2.01E+09

. 65* to 70* 4.37E+10 2.21E+10 1.07E+10 5.27E+09 2.14E+09 70* to 75* 4.92E+10 2.72E+10 1.29E+10 6.17E+09 2.46E+09 75* to 80* 5.03E+10 2.75E+10 1.33E+10 6.13E+09 2.43E+09 80* to 85* 4.32E+10 2.38E+10 1.14E+10 5.15E+09 2.29E+09 85* to 90* 3.98E+10 2.10E+10 1.00E+10 5.00E+09 2.00E+09 35 AEAT-0121

Tabla 28 Cycle 8, Flux >1.0MeV in Vessel Wall at Mid height Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 1.94E+10 1.1lE+10 5.34E+09 2.57E+09 1.13E+09 5* to 10* 2.86E+10 1.51E+10 7.40E+09 3.51E+09 1.48E+09 10* to 15' 3.95E+10 2.11E+10 1.02E+10 4.75E+09 1.89E+09 15' to 20' 4.22E+10 2.32E+10 1.09E+10 5.08E+09 1.99E+09 20* to 25' 3.25E+10 1.77E+10 8.63E+09 3.98E+09 1.63E+09 25' to 30* 2.30E+10 1.24E+10 5.98E+09 2.84E+09 1.19EM9 30' to 35* 1.68E+10 9.38E+09 4.58E+09 2.25E+09 8.86E+08 35' to 40' 1.50E+10 8.00E+09 4.06E+09 1.86E+09 8.50E+08 .

40' to 45* 1.37E+10 7.48E+09 3.73E+09 1.72E+09 7.95E+08 45' to 50* 1.35E+10 7.30E+09 3.43E+09 1.69E+09 7.51E+08 50* to 55* 1.48E+10 7.70E+09 3.86E+09 1.80E+09 8.03E+08 55' to 60* 1.65E+10 9.17E409 4.43E+09 2.13E+09 9.09E+08 60* to 65* 2.31E+10 1.23E+10 6.03E+09 2.85E+09 1.22E+09 65* to 70* 3.31E+10 1.77E+10 8.76E+09 4.18E+09 1.69E+09 70* to 75* 4.28E+10 2.30E+10 1.11E+10 5.18E+09 2.07E+09 75* to 80* 4.01E+10 2.14E+10 1.04E+10 4.84E+09 1.99E+09 80* to 85* 2.80E+10 1.53E+10 7.50E+09 3.59E+09 1.45E+09 85* to 90* 1.99E+10 1.09E+10 5.37E+09 2.61E+09 1.17E+09 Table 29 Cycle 9, Flux >1.0MeV in Vessel Wall at Mid height -

Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O' to i 1.32E+10 1.03E+10 3.17Eru9 2.43E+09 1.01E+09 5* to 10* 2.24E+10 1.17E+10 5.80E+09 2.80E+09 1.19E+09 10' to 15* 2.62E+10 1.41E+10 6.93E+09 3.32E+09 1.32E+09  ;

15* to 20* 2.77E+10 1.47E+10 7.10E+09 3.32E+09 1.32E+09 ,

20* to 25* 2.40E+10 1.26E+10 6.14E+09 2.98E+09 1.23E+09  !

25* to 30* 1.94E+10 1.07E+10 5.14E+09 2.45E+09 1.04E+09 30* to 35* 1.63E+10 8.79EA9 4.38E+09 2.04E+09 8.65E48 35* to 40* 1.32E+10 7.43E+09 3.67E+09 1.73E+09 7.63E+08 40* to 45* 1.01E+10 5 70E+09 2.84E+09 1.39E+09 6.28E+08 45' to 50* 1.03E+10 5.63E+09 2.88E+09 1.37E+09 6.17E+08 50' to 55* 1.24E+10 6.90E+09 3.43E+09 1.61E+09 7.44E+08 55' to 60* 1.63E+10 8.82E+09 4.27E+09 2.03E+09 8.48E+08 60* to 65*, _1,95E+10 1.05E+10 5.12E+09 2.39E+09 1.04E+09 -

65* to 70* 2.32E+10 1.27E+10 6.15E+09 2.95E+09 1.24E+09 70* to 75* 2.71E+10 1.47E+10 7.19E+09 3.31E+09 1.28E+09 75* to 80* 2.59E+10 1.40E+10 6.83E+09 3.11E+09 1.30E+09 -

80* to 85* 2.13E+10 1.18E+10 5.75E+09 2.74E+09 1.17E+09 I

85* to 90* 1.89E+10 1.02E+10 5.08E+09 2.40E+09 1.08E+09 l

36 AEAT-0121

-_..._m.._,..m. . _..._.-,__m . _.

Table 30 Cycle 10, Flux >1.0MeV in Vessel Wall at Mid. height l l

Angle from Distance Through Vessel Wall (T is wall duckness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 1.43E+10 7.62E+09 3.95E+09 1.82E+09 8.14E+08 l 5* to 10* 1.62E+10 8.84E+09 4.61E+09 2.16E+09 8.62E+08 10' to 15* 1.98E+10 1.09E+10 5.45E+09 2.40E+09 9.59E+08 15' to 20* 2.00E+10 1.09E+10 5.46E+09 2.60E+09 1.06E+09 20* to 25* 1.87E+10 1.02E+10 4.87E+09 2.33E+09 9.26E+08 25' to 30* 1.77E+10 9.94E+09 4.87E+09 2.16E+09 9.31E+08 30* to 35* 1.61E+10 9.03E+09 4.45E+09 2.11E+09 9.01E+08 35' to 40* 1.37E+10 7.28E+09 3.65E+09 1.68E+09 7.00E+08 40' to 45* 1.09E+10 6.31E+09 3.05E+09 1.57E+09 6.60E+08 45' to 50* 1.17E+10 6.57E+09 3.13E+09 1.45E+09 6.51E+08 50* to 55* 1.34E+10 7.57E+09 3.72E+09 1.72E+09 7.34E+08 i 55' to 60* 1.64E+10 8.75E+09 4.21E+09 1.97E+09 8.35E+08 l 60* to 65* 1.72E+10 9.45E+09 4.55E+09 2.24E+09 9.37E+08 65* to 70* 1.81E+10 1.01E+10 4.85E+09 2.30E+09 9.14E+08 70* to 75* 2.00E+10 1.07E+10 5.37E+09 2.53E+09 1.03E+09 75* to 80* 1.99E+10 1.02E+10 5.09E+09 2.45E+09 9.78E+08 80* to 85* 1.62E+10 9.25E+09 4.52E+09 2.15E+09 8.64E+08 85* to 90* 1.34E+10 7.38E+09 3.72E+09 1.81E+09 7.76E+08 l

Table 31 Cycle 11, Flux >1.0MeV in Vessel Wall at Mid. height Angle from _

Distance Dirough Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to5' l.31E+10 6.97EW9 3.39E+09 1.68E+09 6.83E+08 5* to 10* 1.51E+10 7.96E+09 3.92E+09 1.81E+09 7.38E+08 10' to 15* 1.68E+10 8.95E+09 4.35E+09 1.91E+09 8.39E+08 I

15* to 20* 1.64E+10 8.85E+09 4.36E+09 1.99E+09 8.63E+08 t

7.64E+09 3.74E+09 1.79E+09 7.70E+08 l

! 20* to 25* 1.44E+10 25' to 30* 1.34E+10 7.63E+09 3.67E+09 1.70E+09 7.44E+08 30' to 35* 1.32E+10 7.27E+09 3.53E+09 1.62E+09 6.31E+08 35' to 40* 1.09E+10 6.15E+09 2.88E+09 1.33E+09 5.79E+08 40* to 45* 8.92E+09 5.00E+09 2.55E+09 1.16E+09 5.34E+08 l

45' to 50* 9.21E+09 4.99E+09 2.51E+09 1.19E+09 5.25E+08 l 5.82E+08 50* to 55* 1.16E+10 6.15E+09 2.97E+09 1.39E+09

- 55' to 60' -1:32E+10 7.30E+09 3.58E+09 1.72E+09 6.84E+08 60* to 65*

. 1.46E+10 7.52E+09 3.88E+09 1.86E+09 7.72E+08 65* to 70* 1.50E+10 8.51E+09 4.07E+09 1.86E+09 7.90E+08

+ 70* to 75* 1.89E+10 9.73E+09 4.81E+09 2.24E+09 9.54E+08 75* to 80* 1.87E+10 1.01E+10 4.72E+09 2.26E+09 9.12E+08 80* to 85* 1.54E+10 8.24E+09 4.12E+09 2.05E+09 8.30E+08 85* to 90* 1.26E+10 - 6.94E+09 3.48E+09 1.67E+09 7.22E+08 37 AEAT-0121

Table 32 Cycles 1 to 4 Combined, dpa/s in Vessel Wall at Mid height Angle trom Distance Through Vessel Wall (T is wall truckness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O' to 5' 4.99E-11 3.04E-i l 1.80E-11 1.04E-Il 5.18E-12 5* to 10' 5.64E-11 3.32E-11 1.99E-11 1.14E-11 5.83E-12 10* to 15' 6.52E-11 3.89E-11 2.26E-11 1.27E-11 6.38E 12 15' to 20' 6.65E-11 3.94E-11 2.24E-11 1.29E-11 6.39E-12 20* to 25' 5.68E-11 3.36E-11 1.97E-11 1.14E-11 5.77E-12 25' to 30* 4.87E-11 2.97E-11 1.77E-11 1.00E-11 5.19E-12 30' to 35' 5.01E-11 2.98E-11 1.74E 11 9.86E-12 5.15E-12 35' to 40' 4.39E-11 2.62E-11 1.51E-11 8.72E-12 4.54E-12 40* to 45' 3.38E-11 2.08E-11 1.23E-11 7.39E-12 4.01E 12 45' to 50' 3.34E 11 2.02E-11 1.24E-11 7.40E-12 4.15E-12 50* to 55' 4.45E 11 2.61E-11 1.51E 11 8.99E-12 4.80E-12 55' to 60* 5.29E-11 3.13E-11 1.81E-11 1.02E-11 ' 5.33E-12 60* to 65* 5.24E-11 3.11E-11 1.80E-11 1.04E-11 5.42E-12 65* to 70- 5.60E 11 3.45E-11 2.00E-11 1.16E-11 5.91E-12 70* to 75* 6.71E 11 3.93E 11 2.26E-11 1.29E-11 6.31E-12 75* to 80* 6.49E-11 3.82E-11 2.23E-11 1.26E-11 6.35E-12 80* to 85* 5.52E-11 3.35E-11 1.95E-11 1.12E-11 5.83E-12 85* to 90* 5.19E-11 3.10E-11 1.80E-11 1.03E-11 5.33E-12 Table 33 Cycle 5, dpa/s in Vessel Wall at Mid height Angle l' rom Distance Through Vessel Wall (I is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge -

u to 5' 5.C E il 3.10E-11 1.:r5 E- 11 1. lie-11 5.93E-12 5* to 10' 5.92E-11 3.55E-11 2.11E-11 1.21E-11 6.33E-12 10' to 15' 7.09E-11 4.23E-11 2.42E 11 1.35E-11 6.83E-12 15* to 20' 7.41E 11 4.33E-11 2.51E-11 1.42E-11 7.12E-12 20* to 25' 6.44E-11 3.84E-11 2.27E-11 1.30E-11 6.60E-12 25' to 30* 5.73E 11 3.47E 11 2.02E-11 1.17E-11 6.14E-12 30*:0 35' 5.78E-11 3.39E 11 1.97E 11 1.14E-11 5.96E-12 35* to 40' 4.98E 11 3.03E-11 1.76E-11 1.01E-11 5.36E 12 ,

2.29E 11 1.37E-11 8.29E 12 4.60E-12 l 40* to 45' 3.74E 11 l 45' to 50' 3.79E-11 2.30E-11 1.38E-11 8.31E-12 4.77E-12 50' to 55' 5.03E-11 3.00E-11 1.74E 11 1.01E-11 5.32E-12 55' to 60* 5.83E-11 3.44E-11 2.00E-11 1.16E-11 5.95E-12 60* to 65* _6.01E-11 3.59E-11 2.11E-11 1.21E-11 6.37E-12 .

65* to 70* 6.57E-11 3.95E-11 2.31E-11 1.30E-11 6.60E-12 70* to 75* 7.33E 11 4.33E-11 2.48E-11 1.41E 11 6.83E-12 75* to 80* 6.96E-11 4.22E 11 2.41E-11 1.37E-11 6.90E-12 .

80* to 85* 6.25E-11 3.70E 11 2.16E-11 1.22E-11 6.35E-12 35' to 90* 5.30E 11 3.26E-11 1.87E-11 1.10E-11 5.77E-12 3g AEAT-0121  ;

i

Table 34 Cycles 6 and 7 Combined, dpa/s in Vessel Wall at Mid-height Angle from Distance Brough Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 5.84E-11 3.47E-11 2.05E-11 1.16E-11 6.03E-12 5* to 10' 630E 11 3.71E-11 2.19E-11 1.25E-11 6.27E-12 10' to 15' 7.03E 11 4.14E-11 2.37E-11 1.32E-11 6.54E-12 15' to 20' 6.87E-11 4.03E-11 2.39E-11 1.28E-11 6.31E-12 20* to 25' 6.23E 11 3.72E-11 2.15E-11 1.23E-11 5.96E-12 25* to 30' 5.72E-11 3.44E 11 2.02E-11 1.17E-11 5.82E 12 30* to 35' 5.60E-11 3.34E-11 1.88E-11 1.06E-11 5.47E-12 35* to 40* 4.92E-11 2.84E-11 1.69E-11 937E-12 4.79E 12 ,

40' to 45' 3.55E-11 2.15E-11 1.33E-11 7.68E-12 4.26E-12 l 45' to 50' 3.51E-11 2.22E-11 1.27E-11 7.57E-12 4.21E-12 1 50' to 55* 4.72E-11 2.86E-11 1.61E-11 9.27E-12 4.86E-12 55* to 60* 5.64E-11 3.36E-11 1.92E-11 1.09E-11 5.42E-12 60* to 65* 5.50E-11 3.20E-11 1.86E-11 1.12E-11 5.69E 12 65* to 70* 631E-11 3.66E-11 2.06E-11 1.19E-11 6.04E-12 70* to 75* 7.26E-11 4.26E-11 2.36E-11 136E-11 6.57E-12 75* to 80* 7.27E-11 4.33E-11 2.48E-11 137E-11 6.55E-12 80* to 85* 6.20E-11 3.74E-11 2.14E-11 1.21E-11 6.14E-12 4 85* to 90* 5.89E-11 3.40E-11 1.99E-11 1.15E 11 5.70E-12 ]

l Table 35 Cycle 8, dpa/s in Vessel Wall at Mid height Angle from Distance Through Vessel Wall (T is wall thickness)

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 2.94E-11 1.84E 11 1.10E-11 6.59E-12 3.56E-12 5* to 10' 4.27E-11 2.48E-11 1.46E-11 8.44E-12 431E-12 10' to 15' 5.92E-11 3.40E-11 1.96E 11 1.10E-11 5.26E-12 15' to 20' 6.28E-11 3.70E-11 2.07E-11 1.16E 11 5.49E-12 20* to 25' 4.89E-11 2.91E-11 1.67E-11 9.49E-12 4.63E-12 25' to 30' 3.52E-11 2.06E-11 1.18E-11 7.05E-12 3.60E-12 30' to 35* 2.53E-11 1.53E-11 9.09E-12 5.45E-12 2.92E-12 35' to 40* 2.21E-11 1.31E-11 7.83E-12 4.70E-12 2.64E-12 40' to 45* 2.07E-11 1.22E-11 7.27E-12 4.29E-12 2.47E-12 45' to 50* 2.04E-11 1.20E 11 6.96E-12 4.22E-12 2.46E 12 1

. 50* to 55* - -219E-11 1.28E-11 7.71E-12 4.58E-12 2.59E-12 55' to 60* 2.50E-11 1.51E-11 8.92E-12 530E-12 2.98E-12 60* to 65* 3.48E-11 2.04E-11 1.19E-11 6.92E-12 3.69E-12

. 65* to 70* 4.90E-11 2.89E-11 1.68E-11 9.55E-12 4.69E 12 70* to 75* 634E-11 3.67E-11 2.06E-11 1.15E-11 5.51E-12 75* to 80* 5.94E-11 3.44E-11 1.95E-11 1.09E-11 5.22E 12 80* to 85* 4.15E-11 2.49E-11 1.44E-11 8.33E-12 4.17E-12 85* to 90* 2.96E-11 1.81E-11 1.09E-11 6.43E-12 3.53E-12 39 AEAT-0121

l 1

Table 36 Cycle 9, dpa/s in Vessel Wall et Mid-height l Angle frorn Distance Through Vessel Wall (T is wall thickness) .

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O'to 5' 2.79E-11 1.72E-11 1.01E-11 5.85E-12 3.10E-12

~

5' to 10' 3.31E-11 1.91E-11 1.02E-11 6.63E-12 3.40E-12 10' to 15* 3.89E-11 2.29E-11 1.32E-11 7.62E-12 3.71E-12 4 15' to 20' 4.10E-11 2.36E-11 1.36E-11 7.71E-12 3.69E-12 20* to 25' 3.56E-11 2.05E-11 1.21E-11 6.92E-12 3.49E-12 25' to 30* 2.93E-11 1.75E-11 1.01E-11 5.83E-12 3.01E-12 30' to 35* 2.44E-11 1.43E-11 8.47E-12 4.94E-12 2.55E-12 35' to 40* 2.00E-11 1.20E-11 7.05E-12 4.18E-12 2.30E-12 40' to 45* 1.55E-11 9.61E-11 5.69E-12 3.56E-12 1.98E-12 45' to 50* 1.55E-11 9.34E-11 5.60E-12 3.38E-12 2.00E-12 50* to 55* 1.89E-11 1.13E-11 6.61E-12 3.94E-12 2.23E-12 55* to 60* 2.46E 11 1.44E-11 8.28E-12 4.83E 12 2.56E-12 60* to 65* 2.94E-11 1.73E-11 9.94E-12 5.69E-12 2.98E-12 65* to 70* 3.49E-11 2.02E-11 1.17E-11 6.80E-12 3.35E-12 70* to 75* 4.02E-11 2.35E-11 1.35E-11 7.59E-12 3.66E-12 75* to 80* 3.84E-11 2.25E-11 1.30E-11 7.34E-12 3.64E-12 80* to 85* 3.22E-11 1.92E-11 1.12E-11 6.55E-12 3.41E-12 85* to 90* 2.82E-11 1.67E-11 9.92E-12 5.74E-12 3.11E-12 Table 37 Cycle 10, dpa/s in Vessel Wall at Mid-height Angle from Distance D1 rough Vessel Wall (T is wall thickness) -

Venical Inner Edge T/4 T/2 3T/4 Outer Edge l l

O'to 5' 2.11E-11 1.27E-11 7.56E-12 4.43E-12 2.48E 12 5' to 10' 2.43E-11 1.46E 11 8.67E-12 5.05E-12 2.57E-12 10' to 15* 2.92E-11 1.73E-11 1.02E-11 5.67E-12 2.78E-12 15* to 20' 3.04E-11 1.76E-11 1.03E-11 5.90E-12 2.89E-12 l 20* to 25* 2.77E 11 1.65E-11 9.55E 12 5.51E-12 2.76E-12 25' to 30* 2.65E-11 1.59E 11 9.08E-12 5.12E 12 2.63E-12 30* to 35* 2.42E 11 1.45E-11 8.48E-12 4.82E-12 2.43E-12 35' to 40* 2.01E 11 1.19E-11 7.11E-12 4.11E-12 2.15E-12 40* to 45' 1.66E 11 1.03E-11 6.14E 12 3.71E-12 2.00E-12 45' to 50' 1.78E 11 1.07E-11 6.23E-12 3.70E-12 1.99E-12 50* to 55* 2.06E-11 1.24E-11 7.30E-12 4.24E-12 2.23E-12  !

55* to 60*_ _2,39E-11 1.41E-11 8.15E-12 4.64E-12 2.38E-12 .

60* to 65* 2.52E-11 1.54E-11 8.70E-12 5.04E-12 2.59E-12 65* to 70* 2.68E-11 1.64E-11 9.58E 12 5.58E 12 2.80E-12 '

70* to 75* 2.99E-11 1.77E 11 1.04E-11 5.82E-12 2.92E-12 -

75* .o SC* 2.92E 11 1.67E-11 9.86E-12 5.60E-12 2.85E-12 80* to 85* 2.45E-11 1.50E 11 8.74E-12 4.97E 12 2.52E-12 85* to 90* 2.02E-11 1.23E 11 7.37E 12 4.39E-12 2.33E-12 40 AEAT-0121

' Table 38 Cycle 11, dpa/s in Vessel Wall et Mid-htight Angle from Distance Through Vessel Wall (T is wall thickness) i Vertical Inner Edge T/4 T/2 3T/4 Outer Edge j 0'to 5' l.91E-11 1.14E-11 6.53E-12 3.93E-12 2.03E-12 l 5* to 10* 2.21E-11 1.29E-11 7.51E-12 4.36E 12 2.18E-12  !

10' to 15* 2.46E-11 1.45E-11 8.39E-12 4.66E-12 2.41E-12 l 15' to 20* 2.42E-11 1.44E-11 8.35E-12 4.72E-12 2.39E-12 l 20* to 25* 2.19E-11 1.28E-11 7.64E-12 4.37E-12 2.26E-12 1 25' to 30* 2.01E-11 1.23E-11 7.21E-12 4.13E-12 2.22E-12 l 30* to 35* 1.94E-11 1.17E-11 6.83E-12 3.81E-12 1.99E-12 35' to 40* 1.61E-11 9.75E-12 5.65E-12 3.26E-12 1.78E-12 40' to 45* 1.34E-11 8.31E-12 4.85E-12 2.93E-12 1.67E-12 45' to 50* 1.39E-11 8.37E-12 4.90E-12 2.96E-12 1.64E-12 50' to 55* 1.71E-11 1.00E-11 5.79E-12 3.35E-12 1.79E-12 55' to 60* 1.96E-11 1.18E-11 6.85E-12 3.93E-12 2.05E-12 60* to 65* 2.13E-11 1.24E-11 7.41E-12 4.22E-12 2.19E-12 65* to 70* 2.26E-11 1.38E-11 8.17E-12 4.56E-12 2.33E-12 70* to 75* 2.76E-11 1.58E-11 9.03E-12 5.15E-12 2.57E-12 l 75* to 80* 2.74E-11 1.64E-11 9.17E-12 5.27E 12 2.58E-12 80* to 85* 2.30E-11 1.37E-11 8.02E-12 4.65E-12 2.39E 12  :

85* to 90* 1.89E-11 1.14E-11 6.79E-12 3.95E-12 2.13E-12 Table 39 Fluence to End of Cycle 11, Flux >0.1MeV in Vessel Wall at Mid-height Angle trom Distance Through Vessel Wall (T is wall thickness) ,

Vertical Inner Edge T/4 T/2 3T/4 Outer Edge O' to 5' 2.20E+19 1.80E+19 1.32E+19 8.96E+18 5.12E+18 5* to 10* 2.48E+19 2.00E+19 1.46E+19 9.83E+18 5.52E+18 10' to 15* 2.00E+19 2.33E+19 1.67E+19 1.09E+19 6.01E+18 15' to 20' 3.02E+19 2.40E+19 1.71E+19 1.11E+19 6.06E+18 20* to 25* 2.62E+19 2.10E+19 1.51E+19 1.01E+19 5.60E+18 -

25' to 30* 2.27E+19 1.87E+19 1.36E+19 9.05E+18 5.11E+18 30' to 35* 2.21E+19 1.77E+19 1.27E+19 8.44E+18 4.86E+18 35' to 40* 1.90E+19 1.53E+19 1.12E+19 7.50E+18 4.36E+18 40* to 45* 1.47E+19 1.23E+19 9.17E+18 6.39E+18 3.87E+18 45' to 50* 1.45E+19 1.22E+19 9.12E+18 6.38E+18 3.98E+18 50* to 55' . .1.91E+19 1.53E+19 1.10E+19 7.56E+18 4.45E+18 55' to 60* 2.26E+19 1.80E+19 1.29E+19 8.57E+18 4.92E+18 60* to 65* 2.30E+19 1.87E+19 1.34E+19 9.09E+18 5.21E+18

. 65* to 70* 2.58E+19 2.11E+19 1.51E+19 1.01E+19 5.65E+18 70* to 75* 3.04E+19 2.41E+19 1.70E+19 1.12E+19 6.06E+18 75* to 80* 2.97E+19 2.36E+19 1.68E+19 1.10E+19 6.02E+18 80* to 85* 2.46E+19 2.01E+19 1.45E+19 9.74E+18 5.51E+18 85* to 90* 2.23E+19 1.81E+19 1.31E+19 8.80E+18 5.05E+18 41 AEAT-0121

m Table 40 Fluence to End of Cycle 11, Flux >1.0MeV in Vess:1 Wall at Mid- .

height ..

Angle trom Distance Through Vessel Wall (T is wall duckness)

Inner Edge T/4 T/2 3T/4 Outer Edge Vertical ,

O'to 5' l.Ol E+19 5.60E+18 2.84E+ 18 1.31E+18 5.46E+17 5* to 10* 1.15E+19 6.23E+18 3.10E+18 1.46E+18 6.0SE+17 10' to 15* 1.37E+19 7.35E+18 3.63E+18 1.66E+18 6.86E+17 15' to 20* 1.39E+19 7.47E+18 3.58E+18 1.67E+18 6.75E+17 20* to 25* 1.20E+19 6.42E+18 3.15E+18 1.47E+18 5.94E+17 25' to 30* 1.02E+19 5.61E+18 2.77E+18 1.31E+18 5.51E+17 30' to 35* 1.00E+19 5.47E+18 2.66E+18 1.24E+18 5.20E+17 8.66E+18 4.74E+18 2.30E+18 1.06E+18 4.53E+17 35' to 40' 40* to 45' 6.65E+18 3.71E+18 1.85E+18 8.83E+17 3.91E+17 45' to 50' 6.63E+18 3.66E+18 1.82E+18 f.69E+17 3.86E+17 8.68E+18 4.75E+18 2.29E+18 1.09E+18 4.57E+17 50* to 55' 55' to 60* 1.03E+19 5.64E+18 2.75E+18 1.28E+18 5.26E+17 60* to 65* 1.08E+19 5.75E+18 2.80E+18 1.31E+18 5.53E+17 1.18E+19 6.44E+18 3.15E+18 1.49E+18 6.10E+17 65* to 70*  :

70* to 75* 1.40E+19 7.58E+18 3.64E+18 1.70E+18 6.81E+17 75* to 80* 1.37E+19 7.40E+18 3.61E+18 1.69E+18 6.77E+17 .

1.13E+19 6.24E+18 3.04E+18 1.42E+18 6.02E+17 80* to 85*

85* to 90* 1.02E+19 5.50E+1S 2.68E+18 1.29E+18 5.36E+17 Table 41 Exposures to End of Cycle 11, dpa in Vessel Wall at Mid height Angle from Distance Through Vessel Wall (T is wall thickness)

Inner Ecge T/4 T/2 3T/4 Outer Edge Venical 1.49E 2 9.01E-3 5.34E-3 3.08E-3 1.59E-3 O'to 5' 1.70E-2 1.00E 2 5.95E 3 3.42E 3 1.74E-3 5' to 10*

1.99E-2 1.18E 2 6.80E-3 3.81E-3 1.90E-3 10* to 15*

2.03E-2 1.19E 2 6.87E-3 3.87E-3 1.91E-3 15* to 20*

20* to 25* 1.75E-2 1.04E-2 6.07E-3 3.4SE-3 1.75E-3 25* to 30* 1.52E-2 9.21E-3 5.40E 3 3.10E-3 1.59E 3 i 30' to 35* 1.48E 2 8.80E 3 5.10E-3 2.91E-3 1.51E 3 35' to 40* 1.28E 2 7.62E 3 4.45E 3 2.56E-3 1.34E 3 40* to 45' 9.91E-3 6.06E 3 3.63E-3 2.16E-3 1.19E 3

,g 1.21E 3 45' to 50* 9.89E-3 6.03E-3 3.60E-3 2.15E-3 50' to 55* 1.28E-2 7.62E-3 4.39E-3 2.58E-3 1.38E-3 55' to 60*, 1.52E 2 9.01E-3 5.21E-3 2.97E-3 1.54E-3 -

60* to 65* 1.57E 2 9.25E-3 5.38E-3 3.12E-3 1.63E-3 I l 65* to 70* 1.75E-2 1.05E-2 6.09E-3 3.50E-3 1.77E-3 70* to 75* 2.07E-2 1.21E-2 6.89E 3 3.92E-3 1.91E-3 .

75* to 80* 2.01E 2 1.19E 2 6.84E-3 3.84E 3 1.90E-3 3.38E-3 1.74E-3  !

80* to 85* 1.68E-2 1.02E-2 5.88E-3 1 85* to 90* 1.51E-2 9.02E 3 5.28E-3 3.05E-3 1.58E-3 42 AEAT-0121

u F

Figure 1 Scan Dawn the Palisades Reactor core support banel

[

352.2351 ..

290.4814 ;-- - - - -' - - insMon e ':;. -

~

" water <

- [

k. '

core shroudl-@91 167.'6400 - - '

::!:!:5:::::::::::::::::::::::::::::::::::  :  ::-

129.78 7;.;; ;;;;;; .;;.;....;;;;..;;.;J;;  ;

                                                                                 ;_                                         .:                 pressure
                                                                                                                           ~

s#

                         !!!!! !!!!!![ !!ihr$I!!!!!!!I!!!!!!!                    l                              '

81.52 ...:. j..g g e .- ,: .: 33.26 "'[" h  != 6 O.0 l l  :

                -15.0                                                               -

8i Q

                                                                                                                                                **      8th

[. ' Concrete

               -63.26   :::::+::::::.e::: :0:.:::::e.::::::+:::::e: -::: i n                                               %'

50cm thick allround l

                         !@i!!s!!!@l@ il@>:!@l@li!$j@jglglgj.
             -111.52    ]ll;;;j;jlllllj;j;lll;;j;.jj!;;:;jjjj;;;j;jjjjj;j;;jjjj     =                                        ,;

l ,.

             -159.78                                                          -
             -167.6400 ;;;::.:;;.:.:g:.:.:;;;;:.:;;.:.::;;: ;;

E '

            -178.2496             ,.                                                                  ?                       :
                                                               ^

h& ' ,

             -231.8061 - M-fi-- - - ~-                                                  '-          '

S s.

             -279.9327                                                                                            !.          f 22 .6778                                        '                            f.ficm thick 224.3188                                            '-

I~ 245.9088 s( 3 247.8088'  :  :

p.3 .

0237.% 88 '

             -455.4849
             -456.1249                                                                                             '

b:dkN '

             -489.7749                                                                                            3                ;
             -512.3299    y'                                       ' vg    -

)

            -562.3299
                                                                                                                ~

43 AEAT-0121

t

                                                                                                 ?/l?              '
                                                                                                     /
                                                                                                  /-

l/ EQ [ :f // $,3 (9 ,/,/ nu

c.-

                                                                                                 %                                                                                             e 5'   $:i                                                                                     ~

y

                                                                                                 *ik b                                                                                                                                                        *
                                                                                                         ./                                                     -    3 -:"

w: I h

                                                  .:.;::                                               \/  w         7, 4                                                                                  ,y l.:::                                                     %"" //////                  s s -       = - =

151.07 152.65 n o 9:: . . . . Ne ~ / y 172.29 Edi t 8.';..

                                                                                                                            , /[/

173.88 190.18 u 8 34 / " " " ' 193.99 h 4 g fg,o 5f.' g :&:. .. [ E -

t. hgN~ 218.44 g ..~.

n.

                                                                                                                                           %ga                                      219.08 g                       E ..                                                         g g                       0                               ^

• 44tg #M)'240.67 zp}

g o g ..

                                                                                                                          ;s.

g.%%ggggggg 242.57 g, R -- ~ 252.73 a E g ' m

                                                                                                                        ...     .5 st .

6. . -

o

                                                                                                                                          '.: .                                             ,U
         %                                                                                                                                   :  . 5.*5.h'55'5 b'Oh'Y.U.DOW&*4Kh'*

e .

         '3 e     '
                                                                                                       .         e                                                                               . .. <

  .   -.       _. . _ - .              . . _ _ _         _ . -   - _ -      --       - . . -       .. ._.       _ _ . _ _ - -             . _ _ _ = _ -

1 J e I Figure 3 Arrangement of Fuel Elements in the Reactor Core i

-m ao me $* 8M E0 E 4

                               ~

A" "A

                                                           %9
                                                                       $o 8 9 c:

G* QE as gs *: h v.E - ai e- - Eg h: e sa y; 32 a"sE. - cc e + i s i 1 2 3 4 5 6 7 8 1

9 10 11 12 13 14 15 16 i

i i l i I 17 18 19 20 21 22 23 24 1 5 ) 25 26 27 28 29 30 31 j l 3 .q I 1 32 33 34 35 36 37 38 i i { 39 40 41 42 43 i i 44 45 46 47 48 49 50 51 dimensions in cm 3 88 RE R dd a5 QN Q 45 AEAT-0121

-_ - ~ . _ -..- - .-. _ . ..-. _-. - . - . . . . - . . . . _ . . - . - . . . . - - - . ~ . - . . . . . - . - - . . . - . . . . . . Figure 4 Section Across a Fuel Element with 216 Fuel Pins 20.955

                                              @@@@@@@@@@@@@@@                                                                     Y
                                                                                                                                                         ~
                                              .@@@@@@.9999...
                                              ..@ ........... 1" 999999999999999
                                              @@@@@@@O@@@@@@@
                                              ..@@e...@                                        ....@

999999999999999

                                              @@@@@@@@@@99999                                                                                             -

9999989694,9@@@@ N/guide rods - dimensions in cm Fuel Element J q;g-+ .. N Fuel Pin 46 AEAT-0121

i Figure 5 Fuel Element Arrangement 999999999999999 999999999999999 *** *6**

                                             @@@@@OO90099999 9999999999999 999999999999 99099999@@                                               9
                                             @@999999                                          99999 9999999                                        @@@999
                                             @@O999999999099                                                        8"i* "'*

999999999999999 999999999999999

                                              @@@990966009999 99999999@@@9999                                                                ~
                                               @@999999@@99@@@

5(a) 208 fuel pins in assembly

    ~

999999999999999 l 999999999999999 . 99999G999CCOOSS ':mfnium me

                                              @@@@9999999999                                                                                        i 9999999999999                                             9                                           l
                                              @@G999996@99                                            99                                            ,
                                              @@@9999@@@@@@99
                                             @@@9999                                           99999 9999999999                                                 s
                                               @@O999999999G99                                                   suie mbe 999999999999999
                                               .999999                          9 99999                    %,

p seeeeeeeeeeeeee 9e9999999999 9999999999 999 5(b) 208 fuel pins with 8 hafnium rods 47 AEAT-0121

Figure 5 Fuel Element Arrangement (continued) ,

                                                                              ~
        @@@@@@@@@@S0000                                                          .
        @@@@@@99999G00@                                            .
        @@@@@O@@@O@@@@@'                                                                   ~

9@@@@@@@@@@O '

         @@OSOS@@@@                                    G
         @@@@@@@@                                  60006
        @@@@@@@                           @@@GOG
         @@@@@@@@@@@ GOGO 8"id*

• d5

         @@OOOO@@@@@@OOO S@@@@@@@@@@@@GW
         @@@@@@@@@@@G@@4L,.
         @@@99009900000S'
         @@@@@@@@@@@GNG
         @@@@@@@@@@@@@@@                                                                    ~

5(c) 152 fuel pins with steel rods on one side G@@@S9999999900 - G00000000000@QG .

                                                                 *

• d* * ***

0@@@@O9000@@900 OOO9999999999 90989066@@@@

          @GOOOO@@OS                                   G GOOOOOOO*-@@@@G 000@@@@                    +@@@@GO GO999999999990G 000999999999000 # 8"id* "d5                                                          .

SGG996@@@@@@@GW GCeeeeeee@@ mace _ , , , , , , ,

          @ G O O O O~O @ @ O @ @ @ G O GO@@@@@@@@@@@@G                                                                         l l          OOOOGG99@@@@@@@

5(d) 160 fuel pins with steel rods on both sides l 48 AEAT-0121 1

y. _ ._. _ . _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _ . _ . _ . . . _ _ _

i  : l o

               . Figure 5                          Fuel Element Arrangement (continued)

I @e9999999999990 999999999999990 . 8* d* *"* l 999990999099999 9999999999999 L 999999999999 9909999999 9 i 90000000 eeeee i e99e999 ee9999 L 9999999999.99999 i- 900999999999099 '8"id* *d' ! Se999999e9999ee l ,999999999999990% ,g ma,

                               'eeC9eOee60eeeeG/

i 999d999999999W l . 009999999990000  : 5(e) 194 fuel pins with steel rods ha corners 1 Figure 6 Drawing of Surveillance and Accelerated Capsules e 5.539 &

h i -d 4.9225--

i V///////4 V/"""f////////////////////////////A y V U Dimensions in cm , 1 49 AEAT-0121

_g o 1 e =

l. Distribution I

l R Snuggerud Consumers Power, PnH=M Plant,27780 Blue Star Memorial l (10 Copies) Highway, Covert, MI 49043, USA. i D Spaar AEAT E.S. Inc.,241 Curry Hollow Road,Pittsburgh, PA15236 USA  ; l A F Avery 30"A32 Winfrith  ! Miss W V Wright 309/A32 Winfrith j i DrIJ Curl 357/A32 Winfrith I l t AEATArchive Bdg 149, Harwell , (2 copies) RPSCD Database 316/A32 Winfrith (Mrs L J Neal) l l I 1 i i . 4 3 50 AEAT-0121

                                                                                . _ _ _ _    _                   ._  - _ _}}