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Final report of SL-1 recovery operation

Author: General Electric Company. Idaho Test Station. SL-1 Project.; U.S. Atomic Energy Commission. Idaho Operations Office.
Publisher: Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information Extension, 1962.
Series: U.S. Atomic Energy Commission.; Idaho Operations Office.; IDO; AEC research and development report.
Edition/Format:   eBook : Document : National government publication : EnglishView all editions and formats
Summary:
In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and  Read more...
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Genre/Form: History
Additional Physical Format: Print version:
General Electric Company. Idaho Test Station. SL-1 Project.
Final report of SL-1 recovery operation.
Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information Extension, 1962
(OCoLC)271452521
Material Type: Document, Government publication, National government publication, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: General Electric Company. Idaho Test Station. SL-1 Project.; U.S. Atomic Energy Commission. Idaho Operations Office.
OCLC Number: 744565753
Description: 1 online resource (1 volume (various pagings)) : illustrations.
Series Title: U.S. Atomic Energy Commission.; Idaho Operations Office.; IDO; AEC research and development report.
Other Titles: Technical report archive and image library.
Responsibility: SL-1 Project, Idaho Test Station, General Electric Company.

Abstract:

In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These things were accomplished by the General Electric Company between May 1961 and July 1962. It was determined that the central control rod was bound in its shroud at a position corresponding to 20- inch withdrawal. Analysis of the pertinent data showed that the amount of reactivity associated with this rod position, inserted at a rate compatihie with manual withdrawal of the rod, can explain the significant evidence which was coliected. No other means of withdrawing the rod was found to be in accordance with the evidence. It was found that the relatively low yield (130 Mw-sec) nuclear excursion produced a water hammer with pressures up to 10,000 psi, which, in turn, caused the pressure vessel to rise some 9 feet in the air. (auth).

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