:„

ARH-SA-232(IAEA -sm-199/87)

64-75J,05--1%

Characterization ofActinide-Bearing Sediments

Underlying Liquid WasteDisposal Facilities at Hanford

Susan M. PriceMASTERLloyd L. Ames

September 1975r-

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ARH-SA-232(IAEA-SM-199/87)

«

CHARACTERIZATION OF ACTINIDE-BEARING

SEDIMENTS UNDERLYING LIQUID WASTE DISPOSALFACILITIES AT HANFORD

Susan M. Price

Physical and Life Science Technology SectionResearch Department

Atlantic Richfield Hanford. Company

Lloyd L. Ames

Water and Land Resources DepartmentBattelle Pacific Northwest Laboratories

September 1975

ATLANTIC RICHFIELD HANFORD COMPANYRICHLAND, WASHINGTON 99352

For oral presentation at theIAEA/ERDA Symposium on TransuraniumNuclides in the Environment

'

San Francisco, CaliforniaNovember 17-21, 1975

ii ARH-SA-232

TABLE OF CONTENTS

Page

ABSTRACT.............. . iii

INTRODUCTION . . . . . . . . . . . . . . . . . . . . . 1

TRENCH CONSTRUCTION AND DISPOSAL HISTORIES . . . . . . 2

TEST WELL LOCATION AND SAMPLING PROCEDURES . . . . . . 3

SAMPLE PREPARATION AND ANALYSIS . . . . . . . . . . . 5

DISCUSSION OF RESULTS . . . . . . . . . . . . . . . . 7

CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . 15

REFERENCES . . . . . . . . . . . . . . · · · · · · · · 16

FIGURES . . . . . . . . . . : . . · · · · · · · · · · 17

iii ARH-SA-232

ABSTRACT

Past Ziquid waste disposat practices at the U. S.Energy Research and DeveZopment Administration's Sanford

Reservation have incZuded the discharges of soZutions con-

taining trace quantities of actinides directZy into the

ground via structures coZZectiveZy termed "trenches".Characterization of samples from two of these trenches, the

216-Z-9 and the 216-Z-lA(a), has been initiated to determine

the present form and migration potentiaZ of pZutonium stored

in sed€ments which received high saZt, acidic waste Ziquids.

AnaZysis of samptes acquired by driZZing has reveaZed

that the greatest measured concentration of Pu, 0106 UCi239Pu/Ziter of sediment, occurs in both fac€Zities just

betow the points of reZease of the waste Ziquids. This

concentration decreases to 0103 FC€ 239Pu/Ziter of sediment

within the first 2 meters of the underZying sediment coZumns

and to %10 Pci 239Pu/Ziter of sediment at the maximum depth

sampled (9 meters). Examination of reZativeZy undisturbed

sediment cores iZZustrated two types of Pu occurrence

responsible for this distribution. one of these types is

composed of Pu partictes (>70 wt% PU02) added to the dis-

posat site in the same form. This "particuZate" type was

"fiztered out" within the upper 1 meter of the sed€ment

coZumn, accounting for the high concentration of, Pu/Ziter of

sed€ment in this region. The second type of Pu (<0.5 wt%

PU02) was originaZZy disposed of as soZubZe Pu(IV). This

"nonparticuZate" type penetrated deeper within the sediment

prof€Ze and was deposited in association with s€ZieatehydroZysis of the sediment fragments.

ARH-SA-232

CHARACTERIZATION OF ACTINIDE-BEARING

SEDIMENTS UNDERLYING LIQUID WASTE DISPOSALFACILITIES AT HANFORD

INTRODUCTION

The U. S. Energy Research and Development Administra-

tion's Hanford Reservation is located in the southeastern

portion of the State of Washington along a 75-kilometerstretch of the Columbia River. Underlying the Hanford area,

in the region of the chemical processing plants, are uncon-

solidated Pleistocene sediments up to 230 meters thick. The

uppermost 60 to 115 m of these sediments lie above the

regional ground water table and are essentially dry. Past

liquid waste disposal practices at Hanford have included the

discharges of solutions containing trace quantities of

actinides directly into these dry sediments via underground

structures collectively termed "trenches". These disposal

operations were carried out under carefully controlled

conditions based upon laboratory studies of waste-sedimentreactions[1] and verified by field investigations.[2] As a

continuation of such studies, a program has been established

to assess the future radiological impact of actinides in the

ground underlying retired trenches and to develop methods

for the long-term control of these contaminants. A major

objective of this program is a detailed characterization ofthe present form and migration potential of plutonium stored

under specific disposal sites. This paper discusses the

initial results of an examination of actinide-bearing sedi-

ments sampled from the two liquid waste disposal facilitiescontaining the greatest Pu inventories at Hanford, the

216-Z-9 and the 216-Z-lA(a) Trenches.

2 ARH-SA-232

TRENCH CONSTRUCTION AND DISPOSAL HISTORIES

The 216-Z-9 Trench is an underground excavation with anactive floor area of 200 m2 located 7 m beneath the top of a

concrete slab flush with the ground surface. ·The walls ofthe cavern slope inward and downward from this cover as

illustrated in Figure 1. Also shown in the Figure is a

generalized geologic cross section of the undisturbed sedi-

ments underlying this facility compiled from surrounding

monitoring wells.

The 216-Z-9 Trench was used to receive liquid wastes

from plutonium processing operations between 1955 and 1962.The waste solutions were partially neutralized salt wastes

(pH 02.5) which at times contained organic materials andundissolved solids. During the 7-yr life of the Trench, thefacility received %4 x 106 liters of liquid wastes contain-ing 038 kg of Pu.[3]

- The 216-Z-lA Trench consists of a herringbone pattern

of clay pipe lying 3.5 m beneath a cover consisting of a

basal impermeable layer blanketed by gravel and backfill.The 100-m long main distributor pipe of the Trench is

divided into three sections, "a", "b", and "c" (Figure 2),

which designate successive points of release of the wasteliquids over the 10-yr life of the facility. A generalized.

geologic cross section of the undisturbed sediments under-

lying this facility, compiled from surrounding monitoring

wells, is shown in Figure 2.

Only the sediments underlying the "a" section were

examined in this investigation. This portion of the Trenchwas used to receive waste liquids from plutonium processing

operations between 1964 and 1966. The content of the

wastes, with a range in pH from 1 to 2.5, was similar to

3 ARH-SA-232

that received by the 216-Z-9 facility. During the 2-yr life

of the 216-Z-lA(a) Trench, the facility received 0106liters of waste solutions containing %30 kg of Pu.

TEST WELL LOCATIONS AND SAMPLING PROCEDURES

The first 60 cm of sediments underlying the floor ofthe 216-Z-9 Trench was the subject of a detailed investiga-

tion conducted in 1972.[3] This study indicated that the

highest surficial accumulation of Pu occurred near thecenter of the Trench floor. Additional samples were subse-

quently obtained from one test well drilled to an initial

depth of 9 m at the site designated in Figure 1.

The basic 216-Z-9 core sampling equipment (Figures 3A

and 38-1) utilized in the 1972 study[3] was composed of a

commercially available hoisting tripod, a cathead-activated

drive hammer, drive rods, and a 10-cm outer diameter (o.d.)

split tube drive sampler. Contamination was controlled by

enclosing sampling operations in a portable glove box

designed to accommodate this equipment. As a precautionary

measure, a slight negative pressure was maintained on the

cavern, and thus the sampling glove box, with an absolutefilter blower assembly. The sampling equipment utilized to

bore the 9-m test well was basically the same. However the

drive rods were strengthened and the size of the sampler

reduced to 7.5 cm (o.d.); modifications that were deemed

necessary in order to sample deeper.

Drilling operations consisted of driving the sampler

0.5 m and raising it to the surface by successively uncoup-

ling the drive rods. Subsequently the sampler was sealed

out and transported to another facility for dismantling. In

order to maintain open hole, casing was driven before

4 ARH-SA-232

sampling was repeated. Throughout the entire operation the

depth of the casing and sample barrel were recorded beforeand after each successive drive in order to calculate what

portion .of the sample was " fill" from sidewall sloughing.

The test well at the 216-Z-lA(a) site was located

adjacent to the initial point of distribution of the wasteliquids (Figure 2). Because of the impermeability of the

overlying gravel layer at the 216-Z-lA(a) site, sampling was

carried out utilizing a conventional cable tool drilling rig

(Figure 3C) rather than the 216-Z-9 equipment. In order to

prevent the release of actinides to the uncontrolled envi-

ronment, the tools of the drilling rig were enclosed by a

containment structure consisting of three barriers. Samp-

ling was carried out within a sealed, plastic primary

enclosure surrounded, as a precautionary measure , by a

larger plastic secondary enclosure (Figure 3D). The top of

the primary and secondary enclesures were equipped withaccordion bellows which accommodated the rise and fall of

the driving weights during drilling operations. A slight

negative pressure was maintained independently on both the

primary and the secondary enclosures utilizing absolutefilter blower assemblies. A tertiary barrier, constructed

of plywood and canvas, surrounded the two plastic barriers

as protection from the weather (Figure 3C).

Sampling operations consisted of driving a 15-cm (o.d.)

drive barrel 1 m and then raising it to the surface. Within

the primary, a 15- x 2.5-cm (o.d.) metal tube was inserted

in the center of the sediments within the drive barrel

(Figure 3B-2) in order to obtain a relatively undisturbedsediment core. The remainder of the sample was then removed

from the drive barrel into premeasured plastic bags, "sealed

out," and transported to another facility for further

5 ARH-SA-232

preparation. In order to maintain open hole, the casing was

subsequently driven approximately 1 m before sampling was

repeated. Throughout the entire operation the depths of the

casing and sample barrel were recorded before and after each

successive drive in order to calculate what portion of the

sample was "fill" from sidewall sloughing.

SAMPLE PREPARATION AND ANALYSIS

The 216-Z-9 split-tube sampler was received from the

field and dismantled in a glove box. Sediments within the

sampler were contained within a solid, 6-cm (o.d.) brass

insert pre-cut into four 15-cm segments (Figure 3B-1).

Contents of the 15-cm inserts, to be nondestructively ana-

lyzed for actinides, were removed and geologically charac-terized. Representative portions of these segments werethen homogenized, measured into either 25- or 500-ml con-

tainers, and transported to the counting laboratory.

Selected 15-cm inserts were sealed, oriented, and packagedto assure minimal disturbance of the sedimentcontents.

The sample containers from the 216-Z-lA(a) test well

were received from the field and reopened in a glove box.The samples were characterized geologically and representa-

tive portions homogenized and proportioned into either 25-or 500-ml containers for nondestructive analysis. The

15- x 2.5-cm (o.d.) cores were also received in the glove

box and packaged to assure minimal disturbance.

Prepared samples from both test wells were analyzed bygamma energy analysis for 239Pu and 241Am. Analyses were

performed utilizing a three coaxial closed end germanium

drifted lithium [Ge(Li)] detector system designed to analyzebulk samples in the low activity range (UCi/liter) at the

6 ARH-SA-232

95% confidence level. Depending upon the estimated activity '

level of the samples, either 25-or 500-ml portions werecounted for 103 seconds.

Based upon gamma energy analysis of the samples,"undisturbed" cores from both test wells were selected forfurther characterization. Upon receipt in the laboratory,

these segments (still in their original liners) were oven-

dried. Subsequently the samples were impregnated by apply-ing a vacuum to one end of the liner while the other end was

situated in epoxy resin. After the resin had cured, thin-

sections were cut from the segments, mounted and polished,and ultrasonically cleaned to remove loose contamination.

Subsequent examination of the samples by autoradiography

indicated that the actinides had not mixed with the plastic

during the impregnation process and that during cleansingonly the loose contamination from grinding had been removed.

Autoradiographs of the core samples varied in exposuretime from 15 min to 3 weeks as a function of actinide con-centration levels. A minimum exposure time was sought toprevent buildup of film background. Kodak Contrast ProcessOrtho  film was used and processed with D-76 film developer.A.special cylindrical solid metal holder was used to lower

background and maintain good film-sample contact duringautoradiography. Micrographs at a magnification of 50 were

made of selected areas on the autoradiograph negatives, andreflected light micrographs made of the same areas on the

samples.

An electron microprobe was used for elemental mappingand chemical analyses of selected areas of the sediment

samples. Scanning across several areas at 2 to 10 um inter-

vals was used to show composition changes with distance.

Feldspar chemical analyses were referred to 32 oxygen atoms.

7 ARH-SA-232

Valid normal analyses were allowed as t 5% of the alkali andalkaline earth atom sums. Feldspar analyses showing losses

in excess of + 5% of the theoretical alkali and alkaline

earth atom sums of 4.0 were assumed to have sustained lossesof these atoms from the feldspar lattice due to alteration

by the acidic, actinide-bearing wastes.

A portion of the sediment sample containing Pu parti-

cles was spread on a flat surface, and the particles located

by autoradiography. Several particles were chosen for

mounting on fine glass rods for powder camera X-ray diffrac-

tion examination. Plutonium particles down to 10 pm in

diameter were positively identified as to the crystal struc-

ture containing the Pu.

DISCUSSION OF RESULTS

The concentration of actinides (239Pu and 241Am) at

selected depths in the 216-Z-9 and 216-Z-lA(a) test holes,

determined by gamma energy analysis, is listed in Table I.

In general the actinide concentration, highest just belowthe bottoms of the facilities, drops off within the first

2 m of the underlying sediment columns. The level of Pu(

activity is at least three orders of magnitude lower in

samples analyzed from the bottoms of the test holes as in

samples analyzed from the tops of the holes. Examination of

selected sediment cores illustrated two types of Pu occur-

rence responsible for this distribution, the "particulate"and the "nonparticulate" .

The "particulate" mode can be described as consisting

of discrete plutonium particles 2 to 25 Um in diameter. The

occurrence of these particles, restricted to the top por-

tions of the sediment columns, accounts for the high

TABLE I

ACTINIDE CONCENTRATION AT SELECTED DEPTHS BELOW THE 216-Z-9 AND216-Z-lA(a) TRENCHES (Determined by Gamma Energy Analysis)

Actinide Concentration, 216-Z-9 Actinide Concentration, 216-Z-lA(a)Depth Below, 239Pu uci/liter 241Am Uci/liter Depth Below 239Pu UCi/liter 241Am Mci/liter

Trench Floor of Sediment of Sediment Trench Floor of Sediment of Sediment00

5 cm 01 x 106 01 x 10550 cm %5 x 103 05 x 102 50 cm 05 x 104 #1 x 1032 m 01 x 103 01 x 102 2 m 05 x 102 05 x 1014.5 m 05 x 102 %5 x 101 4.5 m 05 x 101 05 x 1 0 1

9 m 01 x 101 01 x 1 0 1 9 m 01 x 101 01 x 101

-

*SC

COD:'

10W10

9 ARH-SA-232

concentration of Pu/liter of sediment observed just belowthe points of release of the waste liquids in both facili-

' ties. Plutonium particles, for example, were very scarce30 cm below the floor of the 216-Z-9 Trench.[4] Of 8 of the

particles identified with the small particle X-ray diffrac-

tion technique described, 7 yielded good-to-excellentquality Debye-Sherrer films of the Pu02 diffraction pattern.

The eighth particle yielded no pattern and was probably

noncrystalline polymer. Microprobe analysis of the sameparticles showed that they contained 70 to 95 wt% PuO2• The

diluting effect of the impregnating plastic was probablyresponsible for the <100 wt% PuO2 values because the con-

stituent elements of the plastic (C, H, 0) are not normally

registered on the electron microprobe.

An example of a Pu02 particle occurrence is given in

Figure 4. The sample was from the top 1.5 cm of the sedi-

ment column in the 216-Z-9 Trench. The autoradiograph is a

positive print of a 15-min film exposure with highest acti-

nide concentration represented by the darkest portions ofthe photograph. The top-layered material is a sludge,

consisting of water, Si, Fe, Na, Cr, and K, disposed to the

site during process operations. Loss of water from the

sludge caused desiccation cracks that filled with plastic

during the impregnation process. The other non-alpha-

emitting areas (white) within the samples are cross sectionsof sediment rock fragments. The accompanying electron

scattering and Pu X-ray emission photographs are located as

to area on the autoradiograph at the sludge-sediment con-tact. The Pu X-ray emission photograph shows the location

of the Pu in the sludge, and the discrete Pu particles at an

increased magnification (Pu X-ray emissions are white in

color). The sludge and sand-to-silt-sized sediments acted

as a simple "filtering" system to remove the Pu particles

10 ARH-SA-232

from suspension in the influent wastes to the site.

Plutonium detected deeper within the sediment profile

(below the 1-m depth) was probably contained in the original

waste liquids as Pu(IV) in solution. Examination of selec-

ted sediment samples revealed that this "nonparticulate" Pu

was partially removed in conjunction with silicate hydroly-sis reactions which occurred when the acidicwaste solutions

came in contact with portions of the sand-to-silt-sized rock

fragments. Especially susceptible to hydrolysis reactions

were the glassy portions of the basalt fragments. The

basalt fragments generally comprise 30% of the total volume

of the sediments while the other 70% is composed of rela-

tively low-grade metamorphics with some granitic igneous

rock fragments.

An oversimplified example of such a hydrolysis reaction

on a mineralogic scale would be the following reactioh with

anorthite feldspar:

CaA12Si208 + 2H+ + H2A12Si208 + Ca2+

In the initial step of this alteration process, the feldspar

aluminosilicate framework is essentially left intact. No Si

or Al are solubilized.

The hydrolysis process results in two Pu depositional

areas, proposed as due to solution pH rise. One of the

depositional areas is in each rock fragment at the interface

between (Ca,Na)-feldspar or glass and (H)-feldspar or

(H)-glass. Due to diffusion of alkali cations across the

altered zone, the pH may rise from 2 or less in the solution

to about 9 in the fresh feldspar or glass.[s] The other

depositional area may be in the solution exterior to the

rock fragments. As the solution proceeds down the sediment

11 ARH-SA-232

column, the pH of the solution rises as the hydrogen ions

are removed by the many on-going hydrolysis reactions.Concommitantly the solution content of alkaline earth metal

and alkali metal cations also increases. In both of the

above cases, Pu(IV) may be precipitated as polymer,

Pu(OH)n+4-n, carrying a positive charge. The final product

is Pu(OH)4 or Pu02· The Pu(IV) polymer is formed irrevers-

ibly.[6] Microprobe analyses tend to confirm that the Pu

contained in altered zones of rock fragments is not assoc-

iated with any single element or combination of elements.The Pu appears to occur in all altered rock fragment zones

where a rise in pH could have occurred due to the hydrolysisreaction.

An example of the second mode of Pu occurrence is shown

in Figure 5. The autoradiograph is of a sediment sample1.8 m below the bottom of the 216-Z-lA(a) Trench. Selected

areas of the autoradiograph (A, B, C, and D) were expanded

for examination and the same areas were photographed by

reflected light for comparison. Of special interest is the

basaltic rock fragment shown in cross section in part B.

Note that Pu deposition coincides with chemical attack onthe glassy groundmass at the rim of the fragment. Elemental

X-ray emission photographs of this particular rock fragment

are shown in Figure 6. These photographs give a good quali-

tative indication of the elements extracted during altera-

tion of the groundmass. Calcium, K, and some Mg, Al, and Fe

have been removed from the altered zone, while Si and Ti are

essentially unchanged.

Microprobe scans at 10-um intervals across a portion of

the fragment pictured in Figure 6 for P, Ca, Ti, K, Fe, Al,

and Si are shown in Figure 7. This Figure provides a quan-

tification of the elemental losses expressed as oxides from

12 ARH-SA-232

the altered zone and from the ordinary groundmass. The

large increase in MgO near the interface was probably causedby traversing an olivine or pyroxene crystal in the ground-

mass during the scan. The losses shown by K, Ca, and Al

(and to a lesser extent Fe and Mg) are relatively large from

the altered zone. More complete chemical analyses of the

altered zone, given in Table II (4G, 5G, and 66) show low

total wt% oxides as might be expected when water and hydro-

gen ions have replaced the bulk of the alkaline earth metal

and alkali metal cations in the original glass structure.

Microprobe chemical analyses of feldspars in the

altered and unaltered zones of the fragment in Figure 6 aregiven in Table III (lF, 2F, 3F, and 4F). The feldspar

crystals marked with an asterisk have probably been hydro-

lyzed. However, the feldspars were more refractory in the

acidic environment than the glassy groundmass and their

crystals remain preserved even in the altered zone

(Figure 6). In general, the plagioclase feldspars were more

refractory in all samples examined than many of the meta-

morphic minerals and the glassy basaltic to andesitic rock

fragments.

The Pu concentration associated with the glassy ground-

mass and mineral alteration by the acidic, actinide-bearing

solutions was relatively low. The alpha autoradiograph

shown in Figure 5 required 49 hr of film exposure time to

obtain- a good autoradiograph. The Pu content was generallyless than 00.5 wt% PuO2, although the hydrolysis type of

reaction and associated Pu deposition was found in all of

the core samples examined. In contrast, the Pu particles(>70% PUO2) confined to the upper few cm of the sediment

column required only a few minutes of film contact time for

a good autoradiograph.

TABLE II

GROUNDMASS COMPOSITIONS FROM ELECTRON MICROPROBE CHEMICAL ANALYSES

SampleArea Si02 A1203 K20 MgO (-ag Fe O Ti02 P205 Total

Original Groundmass1-1

W1G 62.1 13.5 2.4 2.5 7.6 10.5 1.9 0.3 100.82G 62.1 13.7 1.7 3.0 7.4 11.4 1.8 0.3 101.43G 62.5 13.3 2.5 2.4 7.4 11.5 2.0 0.5 102.1

Altered Groundmass

4G 62.5 0.4 0.06 - 0.1 2.1 1.3 0.3 69.465G 57.3 4.4 0.4 1.6 0.1 8.8 2.2 0.7 75.56G 56.3 1.8 0.1 - 0.1 7.4 1.8 0.2 67.7

4Xt

i

Ab

TABLE III

COMPOSITION OF LABRADORITE FELDSPARS (Ab = Albite, An = Anorthite,Or = Orthoclase) AND ATOMIC CONTENTS (REFERRED TO 32 OXYGEN ATOMS)AS COMPUTED FROM ELECTRON MICROPROBE ANALYSES

Sample I Ca, K, Na,Area Ab/An/Or Si Al Ca K Na Fe Fe

P1F 40.4:57.8:1.8 10.351 5.490 2.138 0.067 1.493 0.146 3.844 A2F 40.2:58.0:1.8 10.425 5.385 2.139 0.066 1.481 0.160 3.8463F 35.6:61.2:3.2 10.397 5.442 2.230 0.115 1.298 0.106 3.749*4F 38.8:58.6:2.6 10.537 5.260 2.109 0.092 1.401 0.181 3.783*

*Analyses show losses of alkali and alkaline earth cations from thefeldspar structure.

>POm

Vt\.)

15 ARH-SA-232

Characterization of the form of americium, originally

present in the acidic waste liquids as Am(III), was not

dealt with specifically in this study. However it is prob-

able that some of this Am was changed to a hydroxide formwithin the sediment column in association with the silicate

hydrolysis reaction described in the preceding paragraphs.

Additional work is needed before this supposition can beconfirmed.

CONCLUSIONS

From this initial work it can be concluded that two

types of Pu, the "particulate" and the "nonparticulate, "

were deposited within the sediments underlying the216-Z-9 and 216-Z-lA(a) Trenches. However the potential

mobility of these two types, as well as the Am, has yet tobe determined. Leaching studies will be required to ascer-

tain the migration rates of the actinides as a function of

present and projected environmental conditions. In such

studies, the sediment samples would be recharacterized

following the leaching work to determine how the actinideswere redistributed.

Furthermore, the two types of Pu identified in this

study are only proposed to underlie those trenches at

Hanford which received acidic, actinide-bearing wastes. The

form of the Pu contained in sediments underlying thosetrenches which received neutral and basic actinide wastes

must be determined by additional characterization work.

Such work would ultimately provide a basis for evaluating

the migration potential of actinides underlying all liquid

waste disposal facilities at Hanford which received a

particular waste type.

16 ARH-SA-232

REFERENCES

1. R. C. Routson, A Review of Studies on So€Z-Waste

ReZationships on the Sanford Reservation from 1944 to

1967, BNWL-1464, Battelle Pacific Northwest Labora-

tories, Richland, Washington (1974).

2. D. J. Brown, "Migration Characteristics of Radionu-

clides Through Sediments Underlying the Hanford

Reservation," proc. of Symp. May 29-June 2, 1970, IAEA

and ENEA, Vienna, Austria (1967).

3. NucZear Reactivity EvaZuations of 216-Z-9 EncZosed

Trench, A. E. Smith, ed., ARH-2915, Atlantic RichfieldHanford Company, Richland, Washington (1973).

4. L. L. Ames, Jr., Characterization of Actinide Bearing

Soils; Top Sixty Centimeters of 216-Z-9 EnclosedTrench, BNWL-1812, Battelle Pacific Northwest Labora-

tories (1974).

5. R. E. Stevens, Studies on the AtkaZinity of Some

Silicate MineraZs, U. S. Geol. Surv., Prof. Paper 185-A,

(1934).

6. J. M. Cleveland, The Chemistry of Plutonium, Bordon and

Breach, New York, p. 82 (1970).

17 ARH-SA-232

/1f .- f

/ -»TES, ....10 METERS

PLAN

arNJA

TEST WELLA A'0 -

GROUND LEVEL

10 SILTY PEBBLYVERY COARSE TO COARSE SAND

1

u) 20cM SLIGHTLY SILTYll.  COARSE TO MEDIUM SANDE-Ul

  30

  SILTY FINE TO VERY FINE SANDtiO 40 CALICHE

SLIGHTLY SILTY PEBBLY50 VERY COARSE TO MEDIUM SAND

---0 .*#-i- .- - - -- -

60 (WATER TABLE)

CROSS SECTION

FIGURE 1

CONSTRUCTION AND GEOLOGY OF THE 216-Z-9 TRENCH

18 ARH-SA-232

c b a

\\\\ \ \ \\\ \ \ \ \ \ \

A , '- \ \, . I. A'\ \\\\\\ \\ pt \ \ \ . . > > .-3 illliiIlllllll

1 1 1 11 1 111'll I- / / i /10 METERS TEST WELL

PLAN-N h-

A TEST WELL4 L_31 A'-0 0+*. 1 -91 -\ \1 4L10 PEBBLY COARSE TO VERY FINE SAND

--*

  20 SILTY SANDYUJ SLIGHTLY SILTY COARSE COARSE TO FINE PEBBLES  TO MEDIUM SANDJ 30Z- SLIGHTLY PEBBLY -I SANDY SILT  40 - a CALCAREOUS50 SILTY SANDY COARSE PEBBLY SANDY SILT

TO FINE PEBBLES60

-----------

PEBBLY VERY COARSE (WATER TABLE)TO COARSE SAND

CROSS SECTIONFIGURE 2

CONSTRUCTION AND GEOLOGY OF THE 216-Z-lA TRENCH

19 ARH-SA-232

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FIGURE 3

DRILLING AND SAMPLING EQUIPMENT

20 ARH-SA-232

..... 444' .i:Jil 4

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SCANNING ELECTRON MICROGRAPH 631=6  PU X- RAY EMISSION

O.Imm4.1 X-RAY EMISSION

FIGURE 4

PLUTONIUM PARTICLES IN A SAMPLE FROM TOP OF 216-Z-9 TRENCH

21 ARH-SA-232

OPTICAL MICROGRAPHS MICRO AUTORADIOGRAPHS

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FIGURE 5

AN EXAMPLE OF ACTINIDES ASSOCIATED WITH SEDIMENTHYDROLYSIS AND ALTERATION, 216-Z-l A(a) TRENCH

22 ARH-SA-232

66 2/ 304F VG 16 l F 46 3F SG

.*

X-RAY EMISSIONX•RAY EMISSION

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MICRO AUTORADIOGRAPH

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FIGURE 6

DETAILED EXAMINATION OF A SINGLE ALTERED SEDIMENT ROCKFRAGMENT. THE ARROW INDICATES THE SCAN LOCATION SHOWN IN

FIGURE 7. THE NUMBERS AND LETTERS INDICATE ANALYSISLOCATION GIVEN IN TABLES II AND III.

23 ARH-SA-232

ALTERED ORIGINALGROUNDMASS GROUNDMASS

80 1

----r- - -

Si02 ---- \I

/ \/ \A'203 -'-- ,/ \ ----- ----------

LU 60 - \ --\I----0''0 FeO

- - -

X - - -- --- /--0 40''

-----

32

  -D 20- -

.-..-.-.--»0 -1--I-I-'-I-i-'-'-.-,-0-1_.-1-,-,.l i l l i l0 20 40 60 80 100 120 140 160

SCAN DISTANCE, Um

8 , ,  1 1 118.49% '.-.....'.

MgO - --.

(MgO) 0.-il.-.-I- -

CaO -·-·-· * T,i ,-'-·-·-w 6- : r -0Ti02 /,0

- 1 /1X P205 : / ,0 /'  4 -K20 - L./ 1/I

-

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O ---™r'.1 -r:·_._,_._.1- -9 - _r·_ riz--1:----=i- 5----J./5---r--4,---1---0 20 40 60 80 100 120 140 160

SCAN DISTANCE, lim

FIGURE 7

SCAN ACROSS ALTERED GROUNDMASS ANDORIGINAL GROUNDMASS OF ROCK FRAGMENT IN FIGURE 6