ORNL-TM-2490

45
L, ORNL-TM-2490 Contract No. W-7405-eng-26 METALS AM> CERAMICS DIVISION COMPATIBILITY OF HASTELLOY N AND CROLOY 9M WITH NaBFk-NaF-KBF4 (904-6 mole $1 FLUOROBORATE SALT J. W. Koger and A. P. Litman LEGAL NOTICE *c Thla mwrt YI~ prepnred as u1 scEOIult'of DovernmMt mpollllored work. Neither the Unlted hiem, wr the CommlasIon. nor uy perm .CUI.% on behalf of the Commlaslon: A. Makes .epWuMty or represent8tim,exPressed or Implled.with respect to the sccu- m y . completenese. or ~~Iulness of the Wormatlon contained la thla report, or that the we of my Wormatlo% aprmratus, mstbod. or pmcess disclosed In thls mport may not infringe B. hmunen my IllbiUues with respect to the we of. or for &mZea read- fmm the nsa of uy Information. apparatus. method. or +ess dl.cl0sed h thla rem A. uaed tu the he. "pernon actbg 011 behal~ of tbe &mmiaaion" includes uy em- ploy~ or conmetor of the Commlsslon. or employee ol much conmetor. to the extent that much employee or contractor of the Commlsaion, or employee of much contractor ppres. j dls~mlnatas. or provides sccess to. my informath puauaat to his empiopeut or contract 4 wlth the Commlmdon. or his employment with Neb contractor. P 3 : prhtnly owned righ or -. -- APRIL 1969 e . OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee c operated by UNION CARBIDE CORPORATION for the U. S. ATOMIC ENERGY COMMISSION

description

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Transcript of ORNL-TM-2490

Page 1: ORNL-TM-2490

L, ORNL-TM-2490

C o n t r a c t No. W-7405-eng-26

METALS AM> CERAMICS DIVISION

COMPATIBILITY OF HASTELLOY N AND CROLOY 9 M W I T H

NaBFk-NaF-KBF4 (904-6 m o l e $1 FLUOROBORATE SALT

J. W. K o g e r and A. P. Li tman

L E G A L N O T I C E *c

Thla mwrt Y I ~ prepnred as u1 scEOIult'of DovernmMt mpollllored work. Neither the Unlted h i e m , wr the CommlasIon. nor uy perm .CUI.% on behalf of the Commlaslon:

A. Makes .epWuMty or represent8tim,exPressed or Implled.with respect to the sccu- m y . completenese. or ~ ~ I u l n e s s of the Wormatlon contained la thla report, or that the w e of my Wormatlo% aprmratus, mstbod. or pmcess disclosed In thls mport may not infringe

B. hmunen m y IllbiUues with respect to the we of. or for &mZea read- fmm the nsa of uy Information. apparatus. method. or +ess dl.cl0sed h thla rem

A. uaed tu the h e . "pernon actbg 011 behal~ of tbe &mmiaaion" includes uy em- p l o y ~ or conmetor of the Commlsslon. or employee ol much conmetor. to the extent that much employee or contractor of the Commlsaion, or employee of much contractor ppres.

j dls~mlnatas. or provides sccess to. my informath puauaat to his empiopeut or contract 4 wlth the Commlmdon. or his employment with Neb contractor.

P 3

: prhtnly owned r i g h or

-. --

APRIL 1969

e. OAK RIDGE NATIONAL LABORATORY

Oak R i d g e , Tennessee c operated by

UNION CARBIDE CORPORATION for the

U. S. ATOMIC ENERGY COMMISSION

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CONTENTS

Page

A b s t r a c t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Experimental Procedure . . . . . . . . . . . . . . . . . . . . . . 3

5 Materials Section and Fabrication . . . . . . . . . . . S d t Preparation . . . . . . . . . . . . . . . . . . . . 5

Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

NCL-10 (Hastelloy N) . . . . . . . . . . . . . . . . . . 9 NCL-12 (Croloy 9M) . . . . . . . . . . . . . . . . . . . 19

Discussion. . . . . . . . . . . . . . . . . . . . . . . . . . . . 26

Thermodynamics of System Corrosion . . . . . . . . . . . 31

Kinetics of System Corrosion . . . . . . . . . . . . . . 33 S a l t Purification . . . . . . . . . . . . . . . . . . . 36

. Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . 37

Recommendat ions . . . . . . . . . . . . . . . . . . . . . . . . . 37 Acknowledgments . . . . . . . . . . . . . . . . . . . . . . . . . 38

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COMPATIBILITY OF HASTELLOY N AND CROLOY 9M WITH NaBF4-NaF-KBF4 (90-4-6 mole $1 FLUOROBORATE SALT

b *

J. W. Kbger and A. P. Litman

ABSTRACT

The compatibility of a relatively impure (> 3000 ppm impurities ) fluoroborate salt, NaBF4-NaF-KBF4 (90-4-6 mole $1,

L c 4 % - c

with Hastelloy N and Croloy 9M was evaluated i n natural cir- culation loops operating at a maximum temgerature of 605°C with a temperature difference of 145°C. (EL-12) was completely plugged af te r ,1440 h r of operation and the Hastelloy N l o af ter 8760 hr (one year 9 of .operation. All major a3loying elements of the container materials mass transferred during operation as the result of nonselective attack by virtue of the i n i t i a l oxygen and water contamination of the salt. Satu- ration.concentrations of 700 ppm Fe and 470 ppm C r were deter- mined for the fluoroborate salt at 46OOC. The mechanism of corrosion of the system is as follows. ride compounds that are soluble i n the salt are formed i n the hot leg. causes the metal t o de os i t and t o diffuse into the cold leg. This continues unt i l e 1) an ecpilibrium concentration of one or more m e t a l fluorides is reached i n the salt at the cold- leg temperature and these compounds start depositing (e.g., NCL-10) or, (2) the equilibrium constant of the reaction changes so much with temperature that the pure metal i s deposited (e.g., NCL-12).

The Croloy 9Mloop

(NCL-10) was three-quarters plugged

Init ially, metal fluo- '

"he reverse reaction occurs i n the cold leg and

L li

- &

Q

ODUCTION

Nuclear reactors that use molten fluorides as fhels are under development for the dual purpose of power production and thorium con-

versi0n.l Heat generated i n the core region of such a molten-dalt breeder reactor is transferred from the fuel-containing fluoride

s a l t t o a secondary cool rcuit of fluoride salt with

hJ 'MSR Program Semiann. Progr. Rept. Feb. 29, 1968, ORNL-4254.

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then dissipates the heat t o stem2 (MSRE), the nickel-base alloy Hastelloy N has proved t o be an effective

container mater ia for the fluoride salt that contains the fuel and for the LiF-BeF2 diluent.

or combination' (containing both UF4 and ThF4) salts proposed for the

MSBR have been or are being tested for their compatibility w i t h

Hastelloy N and other container materials. the secondary coolant, however, remains open. Test programs have only

considered coolant salts l i ke NaF-ZrF4 and, recently, IXF-BeF;!. While

these salts have demonstrated excellent ccanpatibilitywith Hastelloy N,

there is need for cheaper fluoride mixtures that m e l t a t lower tempera-

tures.

l o w melting point (about 4OO0C, necessary for transferring heat t o super- c r i t i ca l steam), fluoroborate s a l t s - especially NaEF4 - w i t h small

additions of NaF and/or KEP4 have recently become of interest as secon-

dary coolants. L i t t l e is known, however, about the corrosion behavior

In the hl ten-Sal t Reactor Experiment

any potential fissile2 (containing U F ~ fe r t i l e2 (containing ~ h ~ 4 ),

"he choice of a salt for

On the basis of l o w cost (approximately 504/lb) and a relatively

of these salts. The space diagram of the ternary NaF-NaRFc-KBFk

shows that the salt mixture under consideration l i e s corner and has a m e l t i n g point close t o 390°C. Note rities that form BF3OH-c0mpounds significantly lower

of the mixture below that Shawn by the diagram. The fluoroborate salts, especially NaBF4, is higher than

fluoride saltsY3 because i n the temperature range of

system (Fig. 1 )

very near the NaBF4 that oxygen impu-

the melting point

vapor pressure of

that of other interest the sodium

fluoroborate maintains such an equilibriumwith i t s components that a

significant amount of boron trif luoride gas is present i n the system:

NaBF'4 'NaF + BF3(g) . (1 )

2P. R. Kasten, E. S. Bettis, and R. C- Robertson, Design Studies of 1000-W(e) h l t e n Salt Breeder Reactors, ORNL-3996 (August 1966).

3H. S. Booth and D. R. Martin, Boron Trifluoride and Its Derivatives, Wiley, New York, 1949.

ai

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NaF (999)

Little is known about the corrosion behavior of the BF3 gas. A few corro-

sfon experiments ha&,been run with very dry BF3 gas,4 and little appre- I

,a, ?. ciable attack':was found up to 200°C on metals such as brass, stainless

1 steel, nickei, Monel, mild-steel, and ,many others. E $his report describes-the first comprehensive study of the com-

patibility of a relatively impure fluoroborate salt with Rastelloy N and‘Croloy.9M alloys. The experiments were designed to yield infor-

61

ORNL-OWG SE-5560R

NaF*K6F4 (90-4-6 mole %I

KBF.

\/ v/ v /vi v V V 720 ,I (6%P,

. .

Fig. 1. Space Diagram of the NaFLNaBFheKBFb-KP System

mation on temperature gradient mass transfer, the major form of corro- sion in fluoride salt systeks. ~Two loops were operated with NaEIlQ-NaF-KBF4 (90-4-6 mole $1 salt at a maximum temperature of 605°C with a.temperature difference of 145°C to obtain the data presented. These temperatures * match those proposed for fluoroborate salts in a molten,,salt breeder 1 '. reactor. I

EXPERIMENTALPRCCEDURE

!The natural-circulation loops for this program were'of the type shown in Hg. 2. Flow results from the difference in density of the

4F. Rudswell, J. S. Nairn, and K. L. Wilkinson, J. Appl. Chem &, 333 (1961).

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Fig. 2. Natural. Circulation Loops in Test Stands.

C rn * A

\

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b d

x

1

c

P ~

>. L

salt in the hot and cold portions of the loop.

of salt f l o w i n the loops t o be 7 f't/min.

Materials Section and Fabrication

We estimated the velocity

The Croloy 9M material was from Babcock 8~ Wilcox Company heat 18760

and was vapor blasted before fabrication t o remove oxides. NCL-12, was fabricated fYom 0.750-in. -OD tubing with a w a l l thickness of

0.109 in internal standards. The welded areas were torch annealed before and af te r welding.

The loop,

The material was TIGwelded and inspected t o meet existing

The Hastelloy N material was f'rom Union Carbide Corporation, Materials Systems Division heat 5096. The loop, NCL-10, was fabricated from 0.672-in. -OD tubing with a w a l l thickness of 0.062 in. , TIG welded and inspected t o meet the same standards as those required for the

Croloy 9M material. The compositions of both alloys are given i n Table 1.

Table 1. Chemical Composition of Alloy Test Materials

Composition (wt $1 N i C r bb . Fe C M n s P S i

Hastello N 70.8 7.47 15.59 4.01 0.07 0.54 0.005 0. a

89.00 0.09 0.48 0.012 0.010 0.47 (NCL-107

S a l t Preparation

Reactor Chemistry Division a t ORNL. with a fluoroborate salt,

This was their first experience

they prepared it by techniques established

for other fluoride salt raw materials - re la t ively impure NaBFi,

ORNL-3626, p. 146.

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NaF, and KEP4 (90-4-6 mole $1 (Table 2) -were loaded into a container l inedwith nickel, which w a s then evacuated and purged several times with helium.

a helium atmosphere. N e x t , the l i qu id was sparged with helium, Since this caused a large increase in pressure, the reactor vessel was vented. Large quantities of BF3, which had caused the increase in pressure, were

then released. fluoride and hydrogen for several days at 550°C t o remove oxides and a

sparge with hydrogen t o remove structural metal impurities. was then transferred t o a f i l l tank made of Hastelloy N i n preparation

for f i l l ing the loop.

Then, the materials were melted and heated t o 400°C under

Later steps included sparges with a mixture of hydrogen

The salt

The chemical analysis (Table 3) of the prepared salt disclosed two important compositional changes germane t o th i s t e s t series: significant loss of BF3 during preparation, and (2) a high content of oxygen and water.

of th i s salt or the effect of impurities and because information on i t s compatibility with the container alloys was needed quickly, w e decided

t o use it as prepared.

(1) a

Since l i t t l e was k n m about the corrosive behavior

Table 2. Composition of S a l t Mixture Before Purification

Compound

DF4

NaBF4

NaF

&uantities Loaded in Container

5.88

90.20

3.92

6.85

91.61 1.53

Chemical Analysis Element

K 2 -10 Na . 20.00

B 9.60

F 68.30

W

?

.. I

bd

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e, Table 3. Chemic82 Analysis of Salt Before Fill

-~ ~

Element Content (wt $1 K 2.20

Na 25.80 B 9.65 F 60.40

N i < 5& C r 54& Fe 28& S 6' 02 3O0Oa

H20 900, 21ooa

8PeLlrts per million.

OPERATIONS

The hot portion of each loop was heated by sets of clamshell heaters,

with the input power controlled by silicon controlled rect i f iers .(SCR units) and the temperature controlled by a Leeds and Northrup Speedomax H

Series 60 type C. A. T. (current proportioning) controller.

peratures were measured by Chromel-P vs Alumel thermocouples that were spot welded to the outside of the tubing, covered by a layer of Quartz

tape, and then covered with stainless s teel shim stock.

The loop tem-

Before each loop i t h salt , it was degreased with acetone and heated t o 150°C unde t o remove any moisture in the system.

I p

a

t

u

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We checked for leaks with a helium mass spectrometer leak detector while

the interior of the loop was evacuated t o < 5 X torr . All l ines from the f i l l tank t o the loop that were exposed t o the fluoroborate

salt were of the'same material as the loop and were cleaned and tested

~ i n the same manner as the loop. made w i t h stainless s teel compression f i t t ings.

The loops were f i l l ed by heating the loop, the salt pot, and a l l

A l l temporary l ine connections were

connecting l ines t o a minirmlm of 530°C and applying helium pressure t o the salt pot t o force the salt into the loop.

blown on the freeze valves leading t o the dump and flush tanks t o pro- vide a positive salt seal.

able autotransformers fbrnished the heat t o the cold-leg portions. the loop was f i l l ed the heaters were turned off and the insulation was

removed t o obtain the proper temperature difference by exposing portions of the cold leg t o ambient air.

Air was continuously

Tubular electric heaters controlled by vari- Once

The first charge of salt was dumped af te r 24 h r i n the loops a t the maximum operating temperature with some circulation and l i t t l e tempera- ture gradient. that could have been l e f t in the loops. with new salt and put into operation. positive pressure (about 5 psig) was maintained over the salt i n the

loops during operation. of 605°C and with a temperature difference of 145°C.

f i l e around the loops is sham around the schematic of the loop i n Fig. 3.

During circulation each loop contained about 920 g of salt that con-

tacted 1200 cm2 of surface and traveled 254 cm around the loop.

This flush remved surface oxides and other impurities

The loops were then ref i l led A helium cover gas under slight

Each loop was operated at a maximum temperature

A temperature pro-

Temperature excursions indicated a f l o w stoppage in NCL-12 *

(Croloy 9M) after 1440 hr. A t t e m p t s t o drain the loop were &xsuccess-

f'ul, and the loop was' allowed t o cool w i t h the test salt in place. In NCL-10 (Hastelloy N), a significant increase of temperature i n the hot

leg accompanied by a simultaneous temperature decrease in the cold leg occurred a f te r 8335 hr of operation.

cates a disruption in salt flow and can indicate plugging.

perature cycle ceased after 1 hr, and no f'urther incidents occurred

A perturbation of th i s type indi-

This tem-

I

II

L

l I' t

4

1

l-

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ORNL-DWG 68-4t180

SURGE TANK

~

f

CLAMSHELL HEATERS

\ i+-INSULATION

I I I

jI I I

10.C

-

DUMP TANK

Fig. 3. Schematic of MSW Natural Circulation Loop.

0.C

during the l i f e of the loop. The loop was shut dawn af te r 8760 hr (1 year), and the salt was drained'into a dump tank i n a normal manner.

RESULTS

Analyses of loop components and salt were made by standard chemich analysis, metallographic examination, and electron microprobe analysis. The results are discussed beluw.

c NCL-10 (Hastelloy N)

Visual. - A part ia l plug i n the lower part of the cold leg (Fig. 4 ) closed approximately 75$ of the cross-sectional area of the pipe. Analysis s

w

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. TUBE WALL

PLUG

L

Fig. 4. Plug Formed i n NCL-10 (Hastelloy N) Containing NaBF4-NaF-KBF4 (90-4-6 mole $1 After 8760 hr at a Maximum Temperature of 605°C and Tem- perature Difference of 145°C. &. Reduced 40%.

shared this emerald-green plug t o be single crystals of Na3CrF6 (ref. 6 ) .

Smaller amounts of two complex iron fluorides, Na3FeF6 and NaFeF4, were also identified in the cold leg.

Chemical. - The analysis of the salt cake (Fig. 5) collected from

the dump tank of NCL-10 i s given in Table 4. nickel, molybdenum, iron, and chromium i n th i s s a l t were higher than

those of the salt before tes t . 470 ppm.

of the cake, reaching 11.15 and 4.47 w t $ i n these portions, respectively.

The analysis indicated that the water content of the salt - 400 t o 900 ppm

The concentrations of

The average chromium concentrationwas

Due t o cooling, nickel was segregated in the top and bottom portions

6MSR Program Semiann. Progr. Rept., AM. 31, 1967, ORNL-4191, p. 228.

B

-4

t

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td

II

5

-.-

Fig. 5. Drain S a l t Cake From NCL-10 (Hastelloy N) . Table 4. Impurity Analysis: NaBFd-NaF-KEiFh (90-4-6 mole '$1

Analysis (ppm)

N i C r Ivb Fe 0 H20 S

Before t e s t 87 83 7

After test Top slag EL -15' 1.35a

Center layer 90 210 160

146 1400 400 2,6 3000 900 4850

4200 1200 1800 5 1750

3120 270 3540 1.300 2, < 5

Bottom layer 4.47a 1500 7300 1500 3550 2800 < 5,19 3660

%eight percent.

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before t e s t -increased t o 1300 t o 2800 ppm.

much scatter, but we believe that the oxygen content also increased.

The oxygen analyses showed

Presumably these increases are due not t o air inleakage but t o other factors discussed l a t e r i n th i s report.

The crossover l i n e t o the cold leg, the cold leg, and the crossover l ine t o the hot leg all showed slight increases i n wal+ thickness due t o deposition of complex surface layers (Fig. 6). Chemical analysis of the layers disclosed that they were primarily metallic nickel (60 t o 90 w t $) and molybd&mm. A sma.ll quantity of iron was present i n proximity t o the

base metal, but chromium was conspicuously absent. Metallurgical. - Micrometer measurements of the hot leg of the loop

disclosed 1 t o 2 mils of metal loss and slight surface roughening.

(605OC), however, showed a smooth surface w i t h an occasional penetra- tion along a grain boundary (Fig. 7).

section for all the alloying elements showed no compositional gradients.

The chromium trace for this section is given i n Fig. 8 . indicate a general dissolutive attack in the hot-leg section.

Metallographic examination of an area fromthe hottest section

Microprobe traces7 of this hottest

These results

An area a t the entry of the cold leg (520OC) showed a duplex surface

structure, and the areas numbered i n Fig. 9 were analyzed w i t h the micro- probe for the various elements (Fig. 10). The outermost layer, area 1,

is quite high in nickel - trp t o 87 w t $. We believe this is most l ikely a region where nickel deposited during the tes t . taining essentially only molybdenum and nickel. metal surface there is an increase in nickel, a smaller increase in molybdenum, and l i t t l e change in chromium and iron.

increase in nickel and molybdenum metal the concentration of chromium

Area 2 is a region con- Close t o the original

Note that w i t h an

and iron would show a decrease even though there were no change i n the

actual amounts. Figure ll, a photomicrograph of the coldest section NCL-10 (46OOC)

shows a spongy deposit on the surface and a loosely adherent corrosion

product beyond th i s region. the t ightly attached spongy deposit varied in thickness from 0 t o 6 pm

A t higher magnifications, it was seen that

7Data not corrected for absorption, secondary fluorescence or atomic number effects.

r i t

.

5

I

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ORNL-DWG 67-9342R

,’ ,’

I I I 32.5 in.

0.007 inches I

0.007 inches

LOCATION OF Na, Cr F6 PLUG,

NCL 10 SALT: NaBF$NaF-KBF4 (90.4-6 mole %) . TEMPERATURE:605’C,AT= 145”C,TIME = 8760 hr

Fig. 6. &face Layers in NCL-10 (Hastelloy N) After 8760 hr Operation.

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c

P i g . 7. Hastelloy N Hot-Leg Section EL-10 (605°C) s h m at Different Magnifications After 8760 hr i n Fluoroborate S a l t . Glyceria Regia.

Etchant: W

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I 3 2 I

I

I A A

--

Fluoroborate Salt.

ORNL-DWG 68- 9658

I " 0 W

n - n 0

TRACES OF Ni,Fe, AND Mo SHOWED NO GRADIENT

10 20 DISTANCE (p )

30

Chromium i n Hot Leg (605°C) of NCL-10 as t e u o y N) After

40

8760 h r i n

'\

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Fig. 9. Entry t o Cold Leg (520°C) of NCL-10 (Hastelloy N) Operated for 8760 hr i n Fluoroborate Salt. Etchant: Glyceria Regia. (a) 500x. (b) Numbered areas were anaLyzed by microprobe. 2000X.

U

P

bd

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.' 91

E

80

0

\.-.--e-.- Ni

Mo - -

-0-0-

-*-e-.--.-.-

W I c

ORNL-DWG 68-9659

-.-e--t-

Fe -.-.-.-e-

0 io 20 30 40 DISTANCE (p )

Fig. 10. Penetration Curve of Constituents of Hastelloy N a t Cold-Leg Entry (52OOC) of NCL-10 Operated for 8760 h r i n 3luoroborate Salt.

I .

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X

a

Fig. ll. Coldest Section (460°C) of NCL-10 (Hastelloy N) Shown at Different Magnifications After 8760 hr i n Fluoroborate Salt. Glyceria Regia.

Etchant:

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and that it resemble area seen i n the ry t o the cold leg, although much thinner.

and appears, l ike the area 1 of Fig. 9, t o have resulted f’rom nickel deposition (Fig. 12) .

the ba l axe was fluoride compounds. nickel and molybdenum and low in chromium and iron and is an area where

nickel and molybdenum have diff’used into the matrix.

loosely adherent material was possible.

The spongy layer is high in nickel, w i t h some molybdenum,

There was only 63f metal i n th i s spongy layer; The original surface i s high in

No analysis of the

The last section of the loop examined was an area a t the entrance t o the hot leg. was s t i l l low enough (< 530°C) t o make this an area where material was

being deposited. be predominantly nickel, 65 t o 90$ metal and the balance fluoride com- pounds (Fig. 14).

disclosed an unidentifiable crystal structure, probably a mixture of several fluoride compounds. and molybdenum than originally, and, thus, smaller concentrations of

chromium and iron.

I

Although the salt was being heated here, the temperature

Again, a duplex layer was seen (Fig. 13) and found t o

X-ray diff’raction analysis of the fluoride compounds

The surface layer had somewhat more nickel

E NCL-12 (Croloy 9M)

V i s u a l . - When this loop was sectioned for examination, a dark gray plug that completely f i l l ed the cross-sectional area for a vertical distance of 1 in. was found i n the cold leg (Fig. 15). green crystals were see

found against the i n s i salt.

Also, small, i n line, and a metallic layer was

ing i n the cold section and in the

The thin metallic 1 2.5 mils thick was deposited on the

cold-leg section (over one-half the inside of the tubing i

loop). and was found in the f’rozen salt (Fig. 16).

sented about 4$ of the t o t (by mechanical means) fko op. Chemical analysis revealed the layer

In some places, the material had become detached f’rom the tubfng The metallic layer repre-

1 ss of the m t e r i a l (mostly salt) removed

8 t o be 90 wt 4 Fe and 10 wt $ C r meta l .

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ORNL- DWG 68-9660

80

60

h

6? c 3:

z 0 40 I- v) 0

U

- a 2 0 0

20

0

Ni c .. - _. u u v

I

SPONGY I LAYER I -

I

DISTANCE ( p )

Fig. 12. Penetration Curve of Constituents of Hastelloy N i n Coldest Section (460°C) of NCL-10 Operated for 8760 hr i n Fluoroborate S a l t .

tu 0

c G I M m u)

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ti

c

i

ky Fig. 13. Entry t o Hot Leg (530'C) of NCL-10 (Hastelloy N) Shown at Different Magnifications After 8760 hr i n Fluoroborate Sa l t . Glyceria Regia.

Etchant:

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22

DRNL-DWG 68-966f I o 0-0-0-

.-.-41-*-.-*-o ' Ni * ? I

I I I

65-9070 METAL I 60 - BALANCE i

4 1

FLUORIDE SALT I ESTIMATED - I- ORIGINAL f ~ LAYER J SURFACE 3

I 2 t

I P I

1

I I I

I I I

0 I 40

i5 I V

20

Fig. 14. Penetration Curve of Constituents of Hastelloy N i n Hot- Leg Entry (530°C) of NCL-10 Operated for 8760 hr i n Fluoroborate Sa l t .

LJ

d

T

Fig. 15. Iron. Dendrite Plug i n Coldest Section (460°C) of NCL-12 W (Croloy 9M) Operated i n Fluoroborate Salt for 14.40 h r a t a Maximum Tem- perature of 605°C and a Temperature Difference of 145°C. ,

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23

i-

t

6d

Fig. 16. Deposited Metal Layer. at a maximum

metal and salt interface. 30X.

Cross Section of Tubing of NCL-12 (Croloy 9M) Shuwing Loop operated for 14-40 hr i n fluoroborate salt

erature of 605°C and a temperature difference of 145°C. (b) Enlarged view of Reduced 22%. Cross section of NCL-12 tubing.

Page 28: ORNL-TM-2490

24

The dark-gray plug located i n the coldest part of the loop was com-

posed of dendritic crystals. mens in the hot leg (Fig. 171, but we assume that these crystals, grming and circulating i n the salt stream, attached themselves t o the specimens while the loop was cooling.

material on the specimens were essentially pure iron with less than 1% of other elements (sham below).

We found similar crystals adhering to speci-

Chemical. -Chemical analysis showed that the dark-gray plug and the

Elements

Fe

B

C r

Content ( w t

99.00

0.03

< 0.05 Mn < 0.01 Mg Pb

0.05

< 0.02

Si 0.02

m 0.02

cu 0.05

The results of chemical analysis of the green crystals i n the drain leg

are given belm.

Elements

Na

B

F

K

Fe

C r

Mn

w t % - 10-15

2 4 45.9 0.058 18 12

1.5

*

f

The stoichiometry of th i s green deposit, based on th i s analysis, *

color, and other factors, is roughly 2NaF-FeFa-CrF3-BF3, which corresponds W t o chromium and iron fluorides mixed with the salt.

Page 29: ORNL-TM-2490

Fig. 17. h e Iron C tals f k o m NCL-12, Which Ope d for 1440 hr i n Fluoroborate Salt at a Maximum Temperature of 605°C and a Temperature Difference of 145°C. 1OX. Reduced 12%~. (a> Crystals adhering to speci- men, and (b) crystas removed from specimen for photographing.

\

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26

Table 5 gives the composite of the salt before and af te r operation. U The significant changes i n the salt chemistry due t o t e s t axe the increases in the chromium and iron content from 54 t o 255 and 28 t o 700 ppm, respec- tively.

Table 5. Composition of Salt Before and After Operation in NCL-12

Composition ( w t $1 Composition (ppm)

K Na B F N i C r Fe Mo S 0 ~ ~~

Before Test Theoretical 2.10 20.00 9.60 68.3 (calculat ed) Before F i l l 2.20 25.80 9.65 60.4 < 5 54 28 3000

During F i l l 1.98 18.83 9.38 66.2 87 83 146 1400

After Test Hot leg 1.55 19.72 9.29 67.1 265 700 < 20 7 3000

Cold leg 1.89 20.71 9.27 67.3 255 700 < 20 < 2 3200

Metallurgical. -Metallographic examination of the hot-leg loop tubing (Fig. 18) disclosed a fa i r ly smooth surface, and micrometer mea-

surements shared an average 2.5 mil loss fiom a nominal pipe diameter.

Electron microprobe analyses were made on tubing from the hot- and cold-leg sections of NCL-12:

with the metallographic results, shared no iron or chromium concentration gradients; the cold leg analysis (Fig. 20) showed an increase of about

4 w t $ i n iron concentration and a decrease of about 4 w t $ i n chromium

concentration (i . e. , an iron-rich surface layer 1.

the hot-leg analysis (Fig. 191, consistent

. DISCUSSION

The tests described are the first study of the compatibility of a fluoroborate salt with container materials of interest t o molten-salt reactors.

the purification of the salt or the characteristics of mass transfer i n Unfortunately, l i t t l e was known at the time of the t e s t about

i

*

L J

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27

T

8

FA&. 18. for 1440 h r in Fluoroborate Sa l t . Etchant: Picric acid, hydrochloric acid, and ethyl alcohol.

Hot Leg (605'C) of NCL-12 (Croloy 9M), Which Operate

ORNL-DWG 60-9663 I I I I

o Fe

0 0

0 0 0 0

0 90 -OO D " - - o w

- O O

- 0

0 0 0 6 1 - 86 e

F

Fig. 19. Penetration Curve for Iron and Chromium i n the Hot Leg i (605°C) of NCL-12 (Crolo , Which Operated for 1440 hr i n Fluoroborate

salt. CJ

Page 32: ORNL-TM-2490

28

94 0

n U "

n - v - - 90 o * ~ 0 0 o w 0 t9 0 0 o u u 0 0 c, 3 0

2 86 0 42 kt

z a . 8 8 '

0

0 0 0 c

Y

T O - . ' . . a . . . . .-a..-..-- (L t-

i i

z 0 0

e 4

0

0

Fe 0 ' 0 "

.-,.-n Cr .

Fig. 20. Penetration Curve for Ikon and Chromium i n the Cold Leg (46OOC) of NCL-12 (Croloy 9M), Which Operated for 14.40 hr i n Fluoroborate salt.

systems containing such salts.

vented our having any removable specimens, but permanent hot-leg specimens were used in NCL-12.

The use of loops of an old design pre-

Our expectation, based on previous experience with fluoride salts, was that temperature gradient mass transfer of the leas t noble constit-

uent (i.e., chromium and iron) would be the limiting factor. But salt

analyses after the t e s t indicated that all the major alloying elements of the container materials had mass transferred. The nonselective attack was also confirmed by metallographic examination and microprobe analysis

of the loop specimens and piping. In view of the movement of nickel and molybdenum, it is obvious that highly oxidizing conditions, due t o water

and oxygen i n the salt, were present during the operation of the loops. In analyzing NCL-10 and -12, we reviewed earlier studies8 (late

1950's) to single out the cases of mass transfer of nickel and molybdenum.

8J. H. DeVan, unpublished data, 1957-1959.

b;

z

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b

c

i

b

29

We found several instances where this had occurred in salts containing KF.

a NaF-LiF-KF salt (11.5-46.5-42 mole $1 at a max- temperature of 690°C

with a temperature difference of 9OOC. was made before tes t .

One such loop, constructed of HastelIoy N, operated for a year with

No analysis for oxygen or water Examination af ter t e s t disclosed green crystals

embedded in the salt. nickel, iron, molybdenum, and chromium content. X-ray analysis showed that the green crystals were mixtures of sodium and potassium chromium fluoride complex compounds and that most of the XI? present i n the salt

was actually KF-2H20.

Another loop, constructed of Inconel, (~i-18% Cr-lO$ Fe) operated about one-half year with the same salt and a t the same temperatures as

above.

the hot-leg portion of the loop.

contents of the salt were determined; the chromium content had increased significantly from 60 t o 900 ppm. that the salt was about 15% KF-2H20.

pattern of th i s hydrate suggested that it was not formed when the cold melt was exposed t o a i r but was carried as a part of the salt mixture

during operation.' The l i terature s ta tes that KF easily forms a series of crystal hydrates,

whereas LiF and NaF crystallize ar~hydrously.~

is easy t o form KBF3OH and NaBF3OH and that they are quite stable.

S a l t analyses showed significant increases i n

After test , metallographic examination showed heavy attack in

After t e s t only the chromium and iron

X-ray analysis of the salt disclosed

The relatively well-defined x-ray

The compound KFe2H20 is knuwn t o be thermally stable.

It is also noted that it

Thus we have seen that during the molten-salt reactor corrosion

program, salts containi have on occaSion been very aggressive toward

metals. We believe is is the coxtibinedwater asso- ciated with that a lkal i found no leakage of of the loops. This suggests that

. hydrated KF is not r purification process. Paradoxically,

fluoride salt. We again stress that we

it appears that con21

released and w i l l reac

the fluoroborate salt mixture can be

- *€E' + BF3OH . (2)

'1. G. Ryss, The Chemistry of Fluorine and Its Inorganic Compounds, pp. 521-28 and 815-16, AEC-tr-3927, Pt. 2, (February 1960).

c

Page 34: ORNL-TM-2490

30

The generation of HF i n the system leads t o the following reactions with the elements of the container material:

2HF + N i eNiF2 + H2 , (3 1 6HF + b * k F 6 + 3H2 , 2HF + Fe t F e F 2 + H2 , 2HF + C r t C r F 2 + H2 .

(4 1 (5 1 (6

Note that, i n the temperature range of interest, changes in the

standard free energy of formation are not favorable for all the reactions

as written. However, studies on the Fluoride Volatility Processing

scheme" at ORNL shawed that i n a Hastelloy N hydrofluorinator containing fused fluoride salts and HF, chromium and iron were rapidly leached f r o m

the alloy at elevated textperatures (500 t o 650°C) even when the HI? activ- i tywas quite law. the HF to form fluorides soluble i n the melt. It was found that NiF2 i s produced by driving the reaction through the continuous removal of hydro- gen and reaction products, since the free energy of formation (above 49OOC) of the nickel fluoride reaction by Eq. (3) is not favorable.

the same reason, molybdenum can also be forced t o react with HF even though a positive change in free energy is involved. but f i n i t e dissolution rates of molybdenum metal during hydrofluorination

conditions have been reported. l2

In l igh t of the discussion above, we can now consider why two dif-

ferent types of products (i.e., metal and fluoride compounds) were mass transferred in these (NCL-10 and 12) thermal convection loops.

The main reaction is the oxidation of the metal by

For

Evidence of small

11

I t ''A. P. Litman and R. P. Milford, Corrosion Associated with the

Oak R i d g e National Laboratory Fused S a l t Fluoride Volatility Process, paper presented at the Symposium on &sed Salt Corrosion a t the Fall Meeting of the Electrochemical Society, Detroit, Michigan, Oct. 1-5, 1961.

"A. E. Goldman and A. P. Litman, Corrosion Associated With Hydro- fluorination in the.Oak Ridge National Laboratory Fluoride Volatility Process, ORNL-2833 (November 1961).

12A. P. Litman, Corrosion of Volatility Pilot mant MARK I INOR-8 Hydrofluorinator and MARK I11 L Nickel Fluorinator After Fourteen Dissolution Runs, ORNL-3253 (Feb. 9, 1962).

z

t

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31

Thermodynamics of System Corrosion

The cycle of mass transfer init iated by the corrosion of metals by fluoride salts is k n m t o begin in the hotter regions of a loop system w i t h the formation of structural metal fluorides that are soluble in the

salt : -

M+F'-==M!? , ' (7 )

where M is the attacked metal of the container.

The equilibrium constant for Eq. (7) increases with increasing tem- perature; thus, i n a Multicomponent alloy the concentration of the

attacked coqtituent, M, w i l l decrease at loop surfaces at high tempera- ture (weight loss) and increases at surfaces a t l m e r temperatures (weight gains). A t some intermediate temperature, the in i t ia l surface composi- t ion of the structural alloy will be i n equilibrium with the fised salt (no weight change).

In the cooler regions of a closed system, the rate at which the metal is deposited (steady s ta te condition before plugging) is generally equal to the rate at which it diffuses into the metal - a necessity to

maintain i ts equilibrium activity on the surface.

diffusion of the metal i n the alloy i n the cooler regions usually con- t ro l s the rate of corrosion in the hot zone. A t th is stage in the tem- perature-gradient mass-transfer process, weight gains would be found on specimens in the cold section but l i t t l e i f any surface change (deposits) would be seen.

concentration of a metal Eq. (711 does not exceed compound i n the salt at the l a w temperature.

Thus the rate of

3

This generalization is valid only when the equilibrium

e compound in the salt [produced by ation concentration of a metal fluoride

Early studies reported by Grimes13 clearly i l lus t ra te these points. Table 6 shms the chromium concentrations for two salts as functions of the equilibrium between the salts and Inconel or pure chromium. that when the alkali-met

with Inconel a t 800°C it w i l l support a higher concentration of chromium

Note fluoride salt (NaF-fCF-LiF-UF4) i s i n contact

13W. R. Grimes, ANP &uar t. Progr. Rept. June 10, 1956, Om-2106 pp- 96-99.

Page 36: ORNL-TM-2490

32

Table 6. Equilibrium Concentrations of Chromium Fluorides W i t h !bra Sa l t s

Chromium Concentration (ppm)

NaF-KF-LiF-UF4 NaF-ZrF4 -UT4

Calculated salt equilib-

Ncr

Experimental salt equilib- rium with pure chromium

Ncr

rium with Inconel = 0.16 a t 800°C (ref. a) 1660

= 1.0 at 600°C (ref. a> 1100

1400

2400 ~~

'concentration of chromium i n mole fraction.

fluorides (1660 ppm Cr) than it w i l l when it is i n contact with pure chromium at 600°C (U00 ppm C r ) . Accordingly, circulation of such a s a l t i n an Inconel loop would result i n the deposition of essentially pure chromium metal i n the cold zone.

attack would be controlled simply by diffusion of chromium t o the inter- face between metal and salt in the hot zone.

tion of pure iron i n NCL-12 (Croloy 9M) occurred th i s way. a new phenomenon.

frequently in the l a t e 1950's especially i n iron-base alloy loops. 14, l5

Examination of the data for the other s a l t sham i n Table 6

(NaF-ZrFc-UF4) leads t o the conclusion that chromium metal would not plate out i n that system and that any product of mass transfer would be

a fluoride compound. w i l l support a higher concentration of chromium fluorides than it w i l l

In that case, the to ta l rate of

W e believe that the deposi-

This i s not

Rapid plugging by deposition of metal dendrites occurred

A t 600°C th is salt in equilibriumwith pure chromium

crd

t

I

I 4 G . M. Adamson, R. S. Crouse, and W. D. W y , Interim Report on Corrosion by Alkali-Metal Fluorides: Work t o k y 1, 1953, ORNL-2337 (March 20, 1959).

Corrosion by Zirconium-Base Fluorides, ORNL-2338 (Jan. 3, 1961). 15G. M. Adamson, R. S. Crouse, and W. D. Manly, Interim Report on

Page 37: ORNL-TM-2490

33

i

c

i

&Ir

i n contact with Inconel at 800°C. For gross deposition of compounds t o occur, the concentration of the compound at the temperature of interest (cold zone) must exceed the saturation concentration of the metal fluoride \

corrosion product present in the system. We believe that the mechanism i n NCL-10 (Hastelloy N) is similar t o

the one discussed above for the NaF-ZrF4 system and that i n time the con- centration of chroplium - or more accurately the concentration of mixed

metal chromium fluoride - i n the fluoroborate salt at 605°C exceeded the saturation concentration a t 460°C and allowed deposition of large quan-

t i t i e s of complex compounds. Both NCL-10 and NCL-12 operated with the same salt a t the same tem-

perature, yet they were plugged by different mechanisms at different rates. 7$ C r 3 $ Fe) and an iron plug was found i n the Croloy 9M loop (containing

A chromium-rich plug was found i n the Hastelloy N loop (containing

9% C r - b a l Fe). are contained i n alloys w i t h between 7 and 9 w t 4 Cr , the iron content

of the alloy controls the composition of the temperature-gradient mass-transfer deposit.

Kinetics of System Corrosion

With the foregoing

Thus, it appears that when these fluoroborate salts

and evaluation, it is now possible t o deter-

mine when plugging start element a t various times.

n NCL-10 and -12 and the disposition of each

We calculated the oncentrations for chromium and iron i n

NCL-12 from knowledge o weight of the iron plug

of chemical attack (from 1

culations, presented i n T

i n the cold section, 70

amount of these elements a f te r tes t , the an assumed reaction-rate constant and mode

The results of the cal-

, show that the saturation value of iron

xperiments). l6

1120 mg, was exceeded shortly after

130 hr; at that time pure a complete plug.

started depositing and eventually caused

Table 8 shows the same kind of calculations for the operation of NCL-10. In th i s case, it appears that the saturation W u e of chromium

16J. W. Kbger and A. P. Litman, MSR Program Semi-. Progr. Rept., Feb. 29, 1968, ORNL 4254 pp. 218-225.

Page 38: ORNL-TM-2490

Table 7. Calculated Concentration of Alloying Elements from NCL-12 Present i n the S a l t at Various Times

Concentration i n Salt Maximy Average Area Total Deposited i n Deposited

Time Attack Attack Attackedb Material Ribbon Form Fe C r As P l w (hr) (%/an21 (mg/cm2) (an21 Lost (mg) (w) (mg)

(mg) (ppm) (mg) (ppm)

14.4 2 1 650 650 250 360 225 40 25 . 57.6 4 2 650 1300 500 720 450 80 50

130 6 3 6 50 1950 750 1080 675 120 75 1440 20 10 650 6500 2450 1120 700' 400 250' 2530

'Calculated from LW = 2/& p & where K = rate constant, an2/sec a t 6070C,

LW = weight loss, c = concentration of chromium and iron,

P = density of Croloy 9M, and

t = time.

bIncludes surge tank and l ines and one-half of to ta l area.

C By chemical analysis.

Page 39: ORNL-TM-2490

Table 8. Calculated Conceritration of Alloying Elements from NCL-10 : Present in the Salt at Various Times

Concentration in Salt Mt-l&m Average Area TotE!l Deposited on Deposited

Th? Attack& Attack Attackedb Material Cold Fe Cr Ni MJ brig/cm* ) blg/u!l* > ,h?m2) "l.ost bug> Surface

h3) (ppm) brig) (ppm) bg) Cppm) Arlmgp;ukl

bug) (ppm)

4000 38: 19 550 10,450 2100 350 383 420 459 6350 6950 ll50 1260 8760 56 28 556 15,400 3300 509 555c 427 470' 9300 10,OOOc 1560 1700' 220

aCsbul.ated f&m &I = 2/J p & %

where K= rate constant, 10-l* cm*/sec at 607Y, LS? = weight loss,

c = concentration of chromium, iron, nickel, and molybdenum, P = density of Hastelloy N, and t .= time. ,. -

b Includes surge tank and lines and one-half' total area.

Page 40: ORNL-TM-2490

36

i n the cold leg, 470 ppm, was reached af ter about 4000 hr of operation; W a t that time, the chromium, as Na3CrF6, started depositing in large

amounts. 17

It is interesting t o note that i n both cases the amounts of the alloying elements i n the salt and i n the plug were i n about the same rat io as they are i n the base metal.

have shuwn that when constituents of an alloy react w i t h the l iquid medium they w i l l be found i n the liquid and/or deposited i n the ra t io at which they existed i n the alloy. l8 This behavior was found i n both loops of

th i s experiment.

Capsule tes t s and other loop tes t s

Nickel and molybdenum mass transfer products, not normally found i n As has relatively pure fluoride salt systems, also follow this pattern.

been stressed here, the presence of gross quantities of nickel and molyb-

denum indicates strongly oxidizing conditions.

Salt Purification

The salt used in these experiments contained many impurities that

the old techniques, successful with other fluoride salts, did not remove. Since these experiments, improvements have been made i n the fluoroborate

salt preparation. material.

Only very pure salt (99.9%) is now used as start ing In fact, the salt has so few impurities that no steps are

"Several suggestions, besides the removal of the water or oxygen from the system, are offered t o improve the service of the container materials using th i s fluoroborate salt. The most obvious change is t o lower the hot-leg temperature t o 540°C thus lowering the reaction-rate constant an order of magnitude. t o duplicate the previous plugging. temperature i n the cold-leg section. This would raise the saturation value of the elements i n the salt, and depositing would not occur unt i l later. above. broducts from the system on a continuous or batch-wise basis since deterioration (thinning) of the container w a l l by dissolutive corrosion is not a probled i n these systems.

i n Bismuth and Sodium," pp. 106-161 i n Liquid Metals and Solidification, American Society for Metals, Metals Park, Novelty, Ohio, 1958.

It would then take three times as long Another possibility is t o raise the

But this probablywould not improve the l i f e by the same factor as Probably the most important improvement i s removing corrosion

18J. R. Weeks and D. H. G u r i n s Q , "Solid MeW-Liquid Metal Reactions

Y

P

-

Page 41: ORNL-TM-2490

37

f

i

C

taken during processing t o remove the structural metals. procedures for removing water and oxygen are now under study. procedure is also used in the melting and preparation of the fluoroborate

salt t o prevent loss of BF3 vapor and the ensuing change of composition.

In brief, the loaded salt is evacuated t o about 380 tor r and heated t o

150°C in a vessel lined w i t h nickel .and i s held for about 15 hr under these conditions.

volati le impurities) the salt is heated t o 5OO0C, while s t i l l under vacuum, and agitated w i t h helium for a few hours. The salt i s then ready for transfer t o the f i l l vessel.

Purification

A new

If the r i s e i n vapor pressure i s not excessive, (no

CONCLUSIONS

1. Natural circulation loops, fabricated from Hastelloy N and

Croloy 9% that circulated impure (> 3000 ppm impurities) NaBF4-NaF-KBF4 (90-4-6 mole 4) a t a maximum temperature of 605°C with a temperature difference of 145°C evidenced serious temperature-gradient mass transfer.

The mass transfer involved migration of all major constituents of the con- stituents of the container materials and resulted i n restricting f l o w i n the Hastelloy Nloop by deposition of Na3CrF6 crystals and complete plug-

ging of the Croloy 9M loop by iron dendrites. 2. The nonselective corrosion observedwas due t o the presence

of water, chemically bound t o the fluoroborate salts, that reacted during heating t o form HI?.

3. The driving force mass transfer was the temperature depen- dence of the equilibrium constant between the container material con-

st i tuents and the most stable fluoride compounds that can form in the system.

4. The saturation concentrations for iron and chromium in the t e s t

salt at 460°C were found t o be 700 and 470 ppm, respectively.

1. Other, more highly purified fluoroborates should be extensively i

b' tested for corrosion before these coolants can be qualified for molten- salt reactor service.

Page 42: ORNL-TM-2490

38

2. Based on knowledge t o data, iron-base and iron-containing alloys should be avoided in molten-salt reactor coolant circuits that use

fluoroborate salts.

ACKNCWLEDGMEXTS

It is a pleasure t o acknowledge that E. J. Lawrence supervised con- struction, operation, and disassenibly of the t e s t loops during the course of th i s program. for constructive review of the manuscript.

We are also indebted t o H. E. McCoy, Jr. and J. H. DeVan

Special thanks are extended t o the Metallography Grow, especially

H. R. Gaddis, H. V. Mateer, and R. S. Crouse, and t o the Analytical Chemistry Division, Graphic Arts Department, and the Metals and Ceramics Division Reports Office for invaluable assistance.

w

t

i

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39

Om-TM-2490

I

1-3. 4-5.

6-15. 16. 17. 18. 19. 20. 21. 22. 23. 24. 25. 26. 27. 28. 29. 30. 31. 32. 33. 34. 35. 36. 37. 38. 39. 40. 41. 42. 43. 44. 45 46. 47. 48. 49. 50. 5 1 - 52. 53.

' 54. 55. 56. 57.

INTERNAL DISTRIBUTION

Central Research Library 58. E. L. Compere ORNL - Y-12 Technical Library 59. K. v. cook Document Reference Section 60. W. H. Cook

Laboratory Records 61. L. T. Corbin Laboratory Records, ORNL RC 62. B. Cox ORNL Patent Office 63. R. S. Crouse R. K. Ad- 64. J. L. Crawley G. M. Adamson 65. F. L. Culler R. G. Affel 66. D. R. Cuneo J. L. .Anderson 67. J. E. Cunningham R. F. Apple 68. J. M. Dale C. F. Baes 69. D. G. Davis J. M. Baker 70. R. J. DeBakker S. J. Ball 71. J. H. DeVan C. E. m e r g e r 72. S. J. Ditto C. J. Barton 73. A. S . Dworkin H. F. Batman 74. I. T. Dudley S. E. Bea l l 75. D. A. Dyslin R. L. Beatty 76 . W. P. Eatherly M. J. Be l l 77. J. R. Engel N. Bender 78. E. P. Epler C. E. Bettis 79. D. E. Ferguson E. S. Bettis 80. L. M. Ferris D. S. Billington 81. B. Fleischer R. E. Blanc0 82. A. P. Fraas F. F. Blankenship 83. H. A. Friedman J. 0. Blomeke 84. J. H Rye, Jr. R. Blumberg 85. W. K. Furlong E. G. Bohlmann 86. C. H. Gabbard C. J. Borkowski 87. R. R. Gaddis G. E. Boyd 88. R. B. Gallaher J. Braunstein 89. R. E. Gehlbach M. A. Bredig 90. J. H. Gibbons R. B. Briggs 91. L. 0. Gilpatrick H. R. Bronste 92. P. A. Gnadt G. D. m t o n 93. R. J. Gray D. A. Canonico 94. W. R. Grimes S. Cantor 95. A. G. Grindell W. L. Carter 96. R. W. Gunkel G. I. Cathers . 97. R. H. Guymon 0. B. Cavin 98. J. P. Hammond J. M. Chandler 99. B. A. Hannaford F. H. Clark 100. P. H. Harley W. R e CObb 101. D. G. Harman H. D. Cochran 102. w. 0. Harms C. W. Collins 103. C. S. Harrill

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1

104. 105. 106. 107. 108.

109-m . 112. ll3. 114. l l 5 . l l6. l l 7 . 118. 119. 120. 121. 122. 123. 124. 125. 126. 127. 128. 129. 130.

131-140. 141. 142. 143. 144. 145. 146. 147. 148. 149. 150. 151.

152-161. 162. 163. 164. 165. 166. 167. 168. 169. 170. 171. 172 173. 174.

P. N. kubenreich R. E. H e l m s P. G. H e r n d o n D. N. H e s s J. R. Hightawer M. R. H i l l H. W. Hof- D. K. H o l m e s P. P. H o l z R. W. H o r t o n A. Houtzeel T. L. Hudson W. R. Huntley H. Inouye W. H. Jordan P. R. &sten R. J. Kedl M. T. Kelley M. J. Kelley C. R. Kennedy T. W. Kerlin H. T. Kerr J. J. Keyes D. V. Kiplinger S. S. Kirslis J. W. Koger R. B. K o r s m e y e r A. I. Krako-dak T. S. Kress J. W. Krewson C. E. Lanib J. A. Lane C. E. Larson E. J. Lawrence J. J. Lawrence M. S. Lin R. B. Lindauer A. P. Litman G. H. Llewellyn E. L. Long, Jr. A. L. Lotts M. I. Lundin R. N. Lyon R. L. Macklin H. G. MacPherson R. E. IkcPherson J. C. M a i l e n D. L. Ma,nning C. D. Ma,rtin W. R. Martin H. V. Mateer

175. 176.

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