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- W2264759635 abstract "An investigation is under way to determine the feasibility of using Croloy 1 1/4 or 2 1/4 as the containment material for a Liquid Metal Fuel Reactor (LMFR). While nonradioactive experiments and dynamic-loop tests have been made, final evaluation must be withheld until the effects of in-pile exposure are determined. This presents a serious problem since special facilities are required to analyze in-pile loop samples because of the unique combination of high- alpha high- gamma radiation encountered. The alpha radiation from Po/ sup 210/, resulting from neutron capture by the bismuth matrix of the loop, complicates the process of analyzing the high- gamma activity samples, causing many departures from standard highactivity analysis procedures. Design and testing of facilities which were to be installed in the National Reactor Testing Station for the analysis of in-pile test samples are discussed. The complete design is described in detail, along with the planned methods of analysis. Although some of the mechanisms were tested in mock-up, the facility was not completed because the program was cancelled prematurely. (auth)" @default.
- W2264759635 created "2016-06-24" @default.
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- W2264759635 date "1960-02-01" @default.
- W2264759635 modified "2023-09-27" @default.
- W2264759635 title "LIQUID METAL FUEL REACTOR EXPERIMENT. ALPHA-GAMMA ANALYTICAL FACILITIES FOR B & W RADIATION LOOP NO. 2, ETR" @default.
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