ML20235F974
| ML20235F974 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 07/23/1971 |
| From: | Meems J, Quarles L VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20235F939 | List: |
| References | |
| NUDOCS 8707140058 | |
| Download: ML20235F974 (4) | |
Text
_,
h(LM A[44 Uh t UNIVERSITY OF VIRGINIA SCHOOL OP' ENGINEERING AND APPLIED SCIENCE C H ARLOTTESYlLLE. 22909 DIPARTMENT OF NUCLEAR ENGIN EERINg TELEPHONEt 703 624 7196 REACTOR FACILITY July 23, 1971 Dr. Peter A. Morris, Director i
Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D. C.
Ref: Docket No. 50-62 Facility License No. R-66
Dear Dr. Morris,
This is a supplement to our application dated July 21, 1971, for
' Cobalt-60.
Please change the first sentence in that application to-read:
"An amendment is requested to facility license No. R-66,. Docket 50-62, to receive, possess, use and store not more than 70,000 curies of Cobalt-60."
After conversations with members of the DRL staff, we provide the following supplementary information:
1.
It has been calculated that for an activity of 3300 curies one of these Cobalt-60 slugs would have a maximum temperature of 205 C.
The slugs are presently at an activity of about 950 curies each.
The slugs will not melt in air.
2.
Attached is a copy of Flyer Number 6DF340, issued 12 April 1966.
At that time the slugs had an activity of 1700 curies each with a radi-ation field of 2500 R per hour at one yard. The slugs are now at 950 curies each with a radiation field of 1400 R per hour at one yard.
Assuming there are 70 slugs lumped together at a point and neglecting any self shielding, the radiation field would be 9.8x104 R/hr at' one yard.
The gamma dose rate at the surface of the reactor is 50 R/hr per 8 R/hr at 2x106 watt or 1x10 watts. Assuming there is an instantaneous loss of coolant with the shutdown intensity a factor of 20 below the full power intensity, the radiation field at the surface of the reactor would 6 R/hr. A typical radius for the reactor is one foot, so at one be 5x10 yard ~' fro.n an equivalent point source, the fielg would be 1/9 or 5.5x10 5 R/hr. This is greater than 5 times the 9.8x10 R/hr at one yard that would be expected from 70 Cobalt-60 slugs.
8707140050 870702
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PDR ADOCK 05000062 p_
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1 Dr. Peter A. Morris July 23, 1971 l
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l It is concluded that upon complete loss of water from the reactor l
pool, the presence of the Cobalt-60 would not significantly increase the radiation field present because of the reactor. There are no other l
reactor accidents for which the presence of the Cobalt would increase l
the hazard. Also, there are no other accidents with the Cobalt for I
which the presence of the reactor would increase the hazard.
3.
The Cobalt-60 sources are doubly encapsulated in a stainless steel jacket plus an aluminum jacket (2).
The pool water will be sampled and analyzed for Cobalt-60 contamination at intervals not to exceed 40 days.
If the Cobalt-60 activity reaches 5x10-5 pCi/ml, a search for Icaking capsules will be made. Leaking capsules will be isolated to preclude further contamination of the pool water.
References:
l l
(1)
Thomas llorne, " Cold Encapsulation of Cobalt," Hucleonics, 21, 72 (1963).
l (2) Robert D. Jarret, Sr., "U.S. Army Radiation Laboratory,"
Advances in Chemistry Series, 65, 156 (1967) l Very truly yours, J. L. Meem, Director Reactor Facility l
Lawrence R. Quarles, Dean School of Engineering and Applied Sciences l
JLM/lt l
Attch.
Subscribed and sworn before me this date of 1971 Jean M. Ilolliday, Hotary Public My Commission expires:
cc.
J. P. Veerling, Materials Licensing Dr. C. A. Erdman, U. Va.
Reactor Safety Committee, U.Va.
L___
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294 SLUGS O-2 { $425.00
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l FtTNCTIONAL DESCRIPTION The subject materini is being utilized by Natick LnD personnel to irradiato quartermaster food supplies.
Irradiation studies are now limited because the initial activity of 1.34106 cu-.
" ries has doenyed to about 04105 curies.
Suggested uses and/or two le applications Various ; irradiation projects, experimental evaluation for structure s
- 1 ding, high intensity survey tactc thlehness or density gauginw..
bplibration, radiography and
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TECHNICAL DESCRIPTION Slugs, Cobalt-60, 1,700 curies per slug which creates a radiation ficid' of about 2,500 roentgens per hour at one yard. Emitted with each disintegration of the nucleus are high encrpy gamma rays of 1.37 and 1.33 million electron volti..
It is assumed however, that approximately 25% of the gamma ray energy is self absorbed.
Hota particles are 100% absorbed. Cobolt-60 has a half life of about 5.24 years and decays to stable Nickc1-60.
The purity of the Cobalt-60 in each rod was assayed to be 97.5 to 98.5%.
The alumir.um jack-et it, an alloy of No. 1245 with a composition of:
Aluminum greater than 99.45*.,
Cobalt lors than 0.001% and 7,ine less than 0.03%.
Doubic encapsulated, outer Jacket alumln'im 0.0815 In thick, inner jacket staitiless steel O.02 In thick.
Condition of Sources:
Periodic Jeak tests
}erformed on subject sources have shown no indication of leakage.
A microscopic analysis is
_boing performed on the outer aluminum jacket.
Resulb of this analysis will be furnished upon request. Specini procedures are used. for double encapsulation to permit under water storage.
Additional Information:
Since advertised material is radioactive, all technical anp<> cts re3nt-ing to the transfer and issue of the subject materini will'bc the responsibility rsf the tech-nically qualified personnel at the U.S. Army Radiation Laboratory, NatiLA, Msss.
All inquiry regarding the material description, technical qualification for A.E.C., License, BuWeapon Ship-ping Permits, Specini Shipping containers, Eligibility for Transfer, Safety and Security Con-
- trol, and arrangements for outloading shall be referred to Mr. Robert Jarrett, ATIN:
Code AMXRE-FRS, U.S. Army Laboratory, Natick, Mass., Telephonet A/C 617 653-1000, Ext. 145.
liEPOllTING DOCDtENT NO. N00111-6077-KO49 CAbt NO. 4256 3
- .W' THE /SOVE MMlRIAL IS MIUTARY SERVICCS DECL ARED EXCESS 7.~a3*.*
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