DETERMINATION OF RADIATION CONTAMINATION LEVELS DURING CORE I, SEED 2-SEED 3 REFUELING OPERATIONS. Test Evaluation (T-643128) [electronic resource]

A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried ou...

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Bibliographic Details
Online Access: Online Access
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : U.S. Atomic Energy Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1962.
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MARC

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245 0 0 |a DETERMINATION OF RADIATION CONTAMINATION LEVELS DURING CORE I, SEED 2-SEED 3 REFUELING OPERATIONS. Test Evaluation (T-643128)  |h [electronic resource] 
260 |a Washington, D.C. :  |b U.S. Atomic Energy Commission ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1962. 
300 |a Pages: 36 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 02/01/1962. 
500 |a "dlcs-3170102" 
500 |a Duquesne Light Co., Shippingport, Penna. 
520 3 |a A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried out under dry conditions. Maximum contamination levels were also higher, but the general contamination level was lower. The activity of canal water was higher and characterization was made on some of the canal water samples. (D.L.C.) 
536 |b AT(11-1)-292. 
650 7 |a Buildings.  |2 local. 
650 7 |a Contamination.  |2 local. 
650 7 |a Coolant Loops.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Gamma Radiation.  |2 local. 
650 7 |a Measured Values.  |2 local. 
650 7 |a Personnel.  |2 local. 
650 7 |a Power Plants.  |2 local. 
650 7 |a Pressure.  |2 local. 
650 7 |a Radiation Doses.  |2 local. 
650 7 |a Radiation Protection.  |2 local. 
650 7 |a Radioactivity.  |2 local. 
650 7 |a Reactor Core.  |2 local. 
650 7 |a Reactor Fueling.  |2 local. 
650 7 |a Remote Handling.  |2 local. 
650 7 |a Sampling.  |2 local. 
650 7 |a Water Coolant.  |2 local. 
650 7 |a Reactor Technology.  |2 edbsc. 
710 2 |a U.S. Atomic Energy Commission.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
856 4 0 |u http://www.osti.gov/scitech/biblio/4795313  |z Online Access 
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