ML20133H519

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Application for Amend,Extending License SNM-33 to Include U Recovery Process
ML20133H519
Person / Time
Site: 07000036
Issue date: 04/14/1960
From: Dencker E
MALLINCKRODT, INC.
To: Delaney J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20133G976 List: ... further results
References
FOIA-96-343 NUDOCS 9701170203
Download: ML20133H519 (5)


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l M ALLINCKRODT l

NUCLEAR SAINT LO UIS 7, MISSOU RI CENTRAL 18980 U.S.A.

C O R PO R ATIO N i

Plant Hematite, Mineuri i

April 14, 1960 s

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9r. J. C. ':41:ney i

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Oivision of Licensinc and '.:4;;ulation APR 181960 i

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l Mcahington 25, D. C.

$f h. W k cet omw AV Sim ECT3 F.pecial Nucioar ttat,srisi Lioonco No. 33

Dear :

tr Delannyt 6

1 o

l Thic letter is e request for on extension of our special nuclear material 11censo 90. 33 to include the uranium l

recovery process discusand horein.

1:e desire to use scrap asterial of any IFJ>y the uranium content from this process for recovertr errichaent.

In essen' oe, the recovery proooss involves:

1.

Dissolving the morap material in nitrie moid.

2 Extracting the uronium content from this acid solution.

3.

Precipitating the extracted uranium.

4 Iilterin6 the precipitato.

Figure I et the and of this lotter shows a plans view of the vessels to be used in-the extraction and precipitation opera tions.

Vessel dimensiona and vessel separation distances are given on this figure.

Initisi dissolving of the sorop asterial will be done in tanks having safe volumes--onnforslag to date in Table XIII, p. 21 K 1019, Fifth Revision.

Seeb betdtt of sorop t is dissolved will be limited to a safe ',

mass of

> as listed in Tobia XIV, p. 22, K 1019, Pif th Revision.

The " scrap" solution that la formed will-be poured into the tank synton) chown in Figure I.

Here tbs uranium optent will be extreated, prootpitateds Q

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qlh 970114

' AND LEADING PRODUCER O F_ N U C L E A R F ELS PDR FOIA FLOYD96-343 PDR-

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a and filteru'..

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c':t ac"rni brtches of colutic: sill bo ?m:r' d ie / c.r/r.wn.nfore nn extraction ~ filtration rr.n i.a nafo.

The tot c1 uramitm:

content of eno cf tharu ( x tr ct? 'm T'.itrr tion rent 'A ll be loss thrn 3 0 kg. of urculum The proeipl. tate that is formed c'.'.1 be dopocitad in tank 9 in Picc.ro I.

This tank i.2r an stigs sofo void voluco of J9) cubic in hac in ;!hich proc:,.pitato mny be deposited tTcblo XIII, p. 21, x 1019, F1'th Reviolon).

When tho filter is full and the procipitato has boen blown with nitrogen, the cako will bo knocked from this tank into coometrically safe vassals, and romovod from the syatom.

Except for two 5-1/14" diameter tanks (tanks 7 and 9), all tenks in the extraction systo,1 are 5" or ben in diameter.

The two 5-1A" diameter tanks are limited safe by the data in Trble XV, p. 23, K 1019. Fifth Revision.

All intorconnecting piping bot.seen tho tanks in 1" or less.

Except for tanks 7 and 8, all tanks aro et loast 12" apart.

Thic opacing meets the requirement of paragraph "e", p. 26, K 1019, Fif th Revis ion.

A 12" interval was not deemed nocosecry between tanha 7 ond 8 since the bottom of tonk 7 is approximately 1" above the top of tank 8.

Since esob vensol in tho extraction-filtration system has a diamotor of approximately 5", a k value of near.58 is allowod for each vossel.

A h value of.58 permits a maximum solid angle of 3 2 mtoradions to be subtended at any one tank (Table XVII, p. 29, K 1019, Fifth Revision).

For our system, as shown in Figuro I, a maximum solid angle of 1.75 storadians is subtended at tank 6 (see sample calculations at the end of this letter).

In view of the fact that 175 steradians is considerably less than 3 2 storadians, it can be concluded that our system is safe from an interaction 4

standpoint.

d Sincerely, MALLINCKRODT NUCLEAR CORPORATION

t. W. DA E. H. Dencker ano/ Jet I-Q'O M

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