Proton Reaction Analysis for Lithium and Fluorine in Graphite, Using

advertisement

OAK RIDGE NATIONAL

operated by

LABORATORY

UNION CARBIDE CORPORATION

NUCLEAR DIVISION

for the

U.S.

ATOMIC

ENERGY COMMISSION

ORNL-

TM-

2238

HOME

HELP

55

PROTON REACTION ANALYSIS FOR LITHIUM AND FLUORINE I N GRAPHITE,

USING A SLIT SCANNING

TECHNIQUE

R . L. Macklin, J. H. G i b b o n s , and T. H. Handley

NOTICE This document contains information of a preliminary nature and was prepared primarily for internal use a t the Oak Ridge National

Laboratory. I t i s subject to revision or correction and therefore does not represent a final report.

,

1

L E G A L NOTICE -

__--~-__ i

~ r-

-- -- nor

_ _

_ .

-

T h i s report was prepored as on account of Government sponsored work. the Commission, nor ony person acting on behalf of the Commission:

Neither the United States,

A. Mokes any warranty or representation, expressed or implied, w i t h respect t o the accuracy, completeness, or usefulness of the information contained i n t h i s report, or thot the u5e of any information, opporotus, method, or process disclosed i n t h i s report may not infringe p r i v o t e l y owned rights; or

6 . Assumes any l i a b i l i t i e s w i t h respect t o the use of, or for domoges resulting from the use o f any information, apparatus, method, or process disclosed i n t h i s report.

As used i n the above, "person acting on behalf of the Commission" includes any employee or controctor of the Commission, OT employee of such contractor, t o the extent thot such employee or controctor of the Commission, or employee o f such contractor prepores, disseminates, or provides o c c e s s to, any information pursuant t o h i s employment or contract w i t h the Commission, or h i s employment w i t h such contractor.

L-.

__

~

. ..-

~ ~ ~ ~~

__.____

c

ORNL-'IN-2238

C o n t r a c t N o . W-7405-eng-26

Physics D i v i s i o n

PROTON REACTION ANALYSIS FOR LITHIUM

APJD

FLOURINE I N GRAPHITE,

U S I N G A SLIT SCANNING TECHNIQUE

R . L. M a c k l i n , J. H. G i b b o n s , and T. N. H a n d l e y

JULY 1968

OAK R I D G E NATIONAL M O R A T O R Y

Oak R i d g e , T e n n e s s e e

O p e r a t e d by

UNION CARBIDE CORPORATION f o r t h e

U . S . ATOMIC ENERGY COMMISSION

U

*

.

, iii

CONTENTS

Page

Abstract

. . . . . . . . . . . . . . . . . . . . . e .

.

1

Introduction

. . . . . . . . . . . . . . . . . . . . .

.

1

Method and Apparatus

. . . . . . . . . . . . . . . . .

.

2

Standards

. . . . . . . . . . . . . . . . .

O I .

.

.

3

Sample

. . . . . . . . . . . . . . . . . . . . . . . .

* 3

Results and Discussion

. . . . . . . . . . . . . . . .

3

Microscopic Examination of Sample

. . . . . . . . . .

. 4

References

. . . . . . . . . . . .

Y

.

c

W

PROTON REACTION ANALYSIS FOR LITHIUM AND FLUORINE IN GRAPHITE,

USING A SLIT SCANNING TECHNIQUE

R. L. Macklin, J. H. Gibbons, and T. H. Handley

ABSTRACT

Protons from the ORNL 3

MV

Van de Graaff accelerator were brought to a line focus and collimated thru slits of either 0.025 or 0.0075 cm. Cross sectional cuts of graphite samples were moved across the beam to study the distribution of Li and F with depth by measuring the yields of neutrons and of g a m a rays from the reactions TLi(p,n) and lgF(p,q).

A graphite sample exposed to molten fluorides in a loop experiment at the Oak Ridge Research Reactor showed about 20 and 100 ppm (by weight) Li and F respectively, 2 m exposed surface. The observed ratio of Li to F was close to that characteristic of the molten salt down to

3 mm below the exposed surface.

INTRODUCTION

The proton induced reactions 7Li(p,n) and ''F(p,q) have been

1 used to measure the concentration of the target nuclides in graphite.

This can be done in the presence of considerable radioactivity from fission products, making the method attractive for studies of penetra- tion in graphite moderated molten salt reactors.2

1

In the previous work

, the exposed surface of a sample was ground away a layer at a time and the concentrations near each freshly exposed surface measured with a

0.32 cm diameter, 0.1-1 special handling for the radioactive material ground off and introduced considerable delay in the measurements.

- 2 -

METHOD

AND

APPARATUS

The ORNL 3 MV Van de Graaff accelerator proton beam is normally focussed to a cy

1 diameter spot at the target with a magnetic quadrupole strong focus lens. By deliberately detuning this lens the beam can be brought to a horizontal (or vertical) line focus about 1.0 x 0.08 cm. By using several microamperes of current and a metal slit, sufficient beam could be passed through to a sample to perform the analysis over an area 0.0075 cm x 0.60 cm, or with better sensitivity

(compared with background from F impurities in the slit collimator material) 0.025 cm x 0.60 em. With this arrangement, a sample exposed in a reactor can be sectioned, cutting perpendicular to an exposed face and the distribution of 7 L i and with depth studied by simply moving the sample across the proton beam. The apparatus we used for this is

indicated schematically in Fig. 1.

The graphite sample was mounted on a micrometer head and moved in to intercept the beam. The proton beam passing the sample induced a blue fluorescence in the quartz viewing plate at the left so the point at which the edge of the sample just intercepted all of the protons could be easily noted. The profile of the beam passing through the slit was measured with a 0.005 cm A1 foil

glued to the end of the graphite blank. Figures 2

and 3 show the

27Al(p,y) yield from this foil using 0.025 ern and 0.0075 cm gold slits respectively. Slits of tantalum showed too much contamination with fluorine. The slight asymmetry of the scans is probably due to a few protons striking the exposed face of the A1 foil rather than the edge as the blank sample was pulled up out of the beam.

I

.

2.

I

- 3 -

Gamma r a y s were d e t e c t e d by a 12.5 cm d i a . x 17.5 cm l o n g N a I ( T 1 ) c r y s t a l through a 1 . 2 5 ern lead f i l t e r a t t h e s i d e of t h e sample housing.

Neutrons were d e t e c t e d i n t h e s t r a i g h t ahead p o s i t i o n as i n r e f e r e n c e (1).

A s t h e g r a p h i t e b l a n k sample could r e a d i l y be brought i n t o t h e beam t o check t h e background w i t h o u t dismounting t h e sample, w e u s e d 2.06 MeV p r o t o n s ( j u s t below t h e ’Be(p,n) t h r e s h o l d ) throughout, r a t h e r t h a n dropping t h e energy below t h e “ L i ( p , n ) t h r e s h o l d (1.88 MeV) t o check background.

STANDARDS

P r e s s e d samples of g r a p h i t e powder c o n t a i n i n g weighed q u a n t i t i e s of

7

LiF were u s e d as s t a n d a r d s .

SAMPLE

The sample s t u d i e d w a s t a k e n from a molten s a l t convection l o o p exposed i n t h e Oak Ridge Research Reactor

( O m )

year.’ The p i e c e a v a i l a b l e for s t u d y i s shown i n F i g . 4 (ORNL S l i d e No. 74245). The s t r a i g h t e s t s i d e shown i s t h e w a l l of a molten s a l t e x i t channel s e c t i o n e d a x i a l l y a f t e r exposure. The proton b e a m w a s c e n t e r e d a l o n g t h i s s u r f a c e , as n e a r l y p a r a l l e l t o it as i t s i r r e g u l a r i t i e s would p e r m i t .

19 f a s t n e u t r o n s p e r s q u a r e c e n t i m e t e r (79% of i t w i t h 235U b e a r i n g molten s a l t ) and a cracked o u t l e t p i p e w i t h consequent a i r contamination.

RESULTS

AND

DISCUSSION

The homogeneity o f t h e s t a n d a r d s w a s d i s a p p o i n t i n g . Scans of o r i g i n a l and f r e s h l y c u t s u r f a c e s showed c o n s i d e r a b l e v a r i a b i l i t y . The s t a n d a r d d e v i a t i o n a t a s i n g l e p r o t o n beam p o s i t i o n appeared t o b e about

- 4 -

3546. An uncertainty of that size is indicated for the absolute scales of concentration. The standardization was, however, based on the grand average of all our measurements on the 200 ppm (

7

LiF by weight) stan- dard. Until more uniform standards are available or the cause of the observed nonuniformity is better understood, we hesitate to claim greater accuracy for the concentration scale.

The fluorine and lithium concentrations in the sample as a

function of distance from the flow channel surface are shown in Figs.

5

and 6. The rapid decrease in concentration in the first ten mils or so (0.025 cm) is expected. The persistence of moderate concentrations to much greater depths is puzzling. Figure 7 shows the ratio of F to

Li concentration. The ratio is persistently near the ratio characteristic of the molten salt mixture rather than that for the LiF molecule or the progressively lower values expected for free ionic diffusion. It has

4 been suggested that the bulk of the material seen at depth may repre- sent liquid phase intrusion via a slant crack. It should be noted that the promotion of graphite wetting by the air contamination experienced in the ORR Loop should make smaller cracks than usual effective in this regard.

MICROSCOPIC M A M I N A T I O N OF SAMPLE

The graphite sample was viewed (x 10 and x 2 0 magnification) with a binocular microscope. The surface is relatively quite rough, with saw markings a few thousandths of an inch deep and pock-marked with many voids several thousandths of an inch in diameter. There is evidence of at least one long groove or crack in the sample at about 20' inclination to the exposed surface. The surface is also irregularly

W t

- 5 - discolored, reminiscent of differential heating effects. When wetted with acetone numerous bubbles r o s e to the surface, clearly implying penetration of the liquid into sub-surface voids. In short, this sample shows gross irregularities and imperfections compared to the sample

1 taken from the MSRE that we studied earlier.

- 6 -

REFERENCES

1. R . L. Macklin, J . H. Gibbons, E. R i c c i , T. Handley, and D. Cuneo, t o be p u b l i s h e d i n Nuclear A p p l i c a t i o n s .

2 . H. G. MacPherson, Power Englneering, January, 1967, p. 2-8.

3 . Molten-Salt Reactor Program Semiannual P r o g r e s s Report f o r P e r i o d

Ending August 31, 1967. ORNL-4191, P a r t 1 5 .

4. E . G. Bohlmann, p r i v a t e communication. v

.

W

A

- 7 -

FIGURE CAPTIONS

Fig.

1

-

Schematic side view of the scanning system. The graphite sample

(from a specimen exposed to molten salts containing 7Li and

19F) is cut so that the exposed surface is uppermost in the

7 figure. The Li(p,n) and 19F(p,q) yields indicate concentration as a function of depth as the sample is moved up across the collimated proton beam.

Fig. 2

-

Proton beam profile using the .O25 ern slit-collimator as measured by the 27Al(p,y) reaction yield from a .005 em A1 foil seen edge-on. The small random deviation of the points from the curve is largely an indication of mechanical precision and reproducibility in the experiment (about 0.0003 em).

Fig. 3

-

Proton beam profile for the .0075 em slit-collimator measured using the .OO5 em A l foil. At the left the beam is hitting clean graphite, whereas at the right it can graze tangentially the flat face of the A1 foil (see Fig. 1) producing a slight tail in the composite resolution function shown.

F i g . 4 -

L o c a t i o n a n d o r i e n t a t i o n of t h e sample c u t from t h e

1967 ORR

Loop Specimen. The molten salt flow was largely upwards through the drilled holes and channels shown in the photograph.

Fig.

5

-

Fluorine concentration as a function of depth in the ORR Loop graphite sample. The data taken at two slit widths are self- consistent. The results cannot be accounted for by simple ionic diffusion and may reflect non-homogeneous structure of the graphite.

Fig. 6

-

Lithium concentration as a function of depth in the ORR Loop graphite sample. The data obtained with the two slit-collimators

- a - are self-consistent. The lithium concentration beyond 100 mils depth decreases more rapidly than expected.

Fig. 7

-

Mass concentration ratio, F/Li, versus depth. The closeness of the ratio observed to that typical of the bulk salt suggests that most of the material found (at depths down to 30 mils) may represent a liquid intrusion.

W

- 9 -

MICROMETER

DRIVE MOUNT

ORNL-DWG 68-655f

CLEAN GRAPHITE FOR BACKGROUND CHECK

0 . 0 0 5 c m AI FOIL FOR SCANNING B E A M PROFILE

GAMMA RAYS

A-

NEUTRONS

MICROMETER

DRIVE MOUNT

0.0075 x 0 . 6 0 c m COLLIMATING S L I T

SAMPLE TO BE SCANNED

CONVERGING

PROTON B E A M

(2.06 MeV)

Fig. 1

-

10

-

6000

5000

W

2

4000 k z

3

8

W

$

-J

W

U

2000 io00

ORNL- DWG 68-6552 t

--I----

40 42 44 46 48 50 52

DISTANCE (mils)

Fig. 2

54 56 58 60

Y

-

11

-

ORNL- DWG 68- 6553

4

0,000

8000

6000

4000

2000

0

44 16

18

20 22

DISTANCE

(mils)

24

Fig.

3

26 28

-

12

-

ORNL- DWG 68-6736

SURFACES O F

MOLTEN SALT FLOW CHANNELS

CROSS SECTIONAL

SURFACE CUT

A F T E R EXPOSURE

- - - ---

-------a

PROTON B E A M POSIT10

AT VARIOUS DISTANCE

FROM EXPOSED SURFACE

/

/ COLLIMATED

PROTON B E A M

Fig.

L

L

-

1 3

-

.

ORNL-DWG 68-6556

40,000

5000

2000

1000

E

2

500

Y

sp

In m

+ I c

LL

200

100

50

20

2 5 10 20 50 100

DEPTH BELOW SURFACE (mils)

200 500

Fig. 5

- 14 -

ORNL-DWG 68-6554 io00

500

200

-

400

E

CL

6

In rr)

+I

.-

-I b

20

(0

5

2

'

4 i 2

'

!

I

,

1 , l . l

5

i o 20

I

I

50

1 1 1 1 '

I

400 200 500

DEPTH BELOW SURFACE (mils)

Fig. 6

-

15

-

ORNL-DWG 68-6555

I000

500

200

0

F 50 a tY

.- r-

-I

\ 2 0

5

2 i 2 5 io

20 50 100

DEPTH BELOW SURFACE (mils)

200 500 1000

Fig. 7

- 17 -

ORNL-TM-2238

1. A. M. Weinberg

2. H. G. MacPherson

3. E. P. Wigner

4. G. E . Boyd

5.

J.

L. Fowler

6. E. L. Compere

7. F. C u l l e r

8. L. Dresner

9. R . B. Evans, I11

1 0 . M. S. Wechsler

11. D. K. Holmes

12. S. S. K i r s l i s l 3 * D. R. Cuneo

14. F. F. Blankenship

15. W. H. Cook

16. W. S. Lyon

17. M. T. Kelley

18. E. R i c c i

19. T. H. Handley

20. E . S. B e t t i s

21. E. G. Bohlmann

22. R . B. Briggs

23. S. J . D i t t o

24. W. P. E a t h e r l y

25. D . E . Ferguson

26. W. R . Grimes

27. A. G. G r i n d e l l

28. P. N. Haubenreich

29. P. R . Kasten

30. R . E. MacPherson

31. H. F. McDuffie

32. H. E. M ~ C O Y

33. R . L. Moore

34. E. L. Nicholson

35. L. C . Oakes

36. A. M. P e r r y

37-39. M. W. Rosenthal

40. Dunlap S c o t t

41. M. J. Skinner

42. R . E. Thoma

43. J. R. Weir

44. M. E. Whatley

45. J. C. White

46. D. S. B i l l i n g t o n

DISTRIBUTION

47-48. C e n t r a l Research Library

49. Document Reference Section

50-52. Laboratory Records Department

53. Laboratory Records, ORNL R . C .

54. ORHL P a t e n t Office

55-69. DTIE

70. Lalrsratory

and University

Division, OR0

7 1 - 9 - R. L. Macklin

Download