Sampling and Examination Methods Used for Three Mile Island Unit 2
Author:
Affiliation:
1. Idaho National Engineering Laboratory EG&G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83415
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT89-A27678
Reference16 articles.
1. R. L. NITSCHKE, “Analysis Data on Samples from the TMI-2 Reactor Coolant System and Reactor Coolant Bleed Tank,” GEND-INF-021, EG&G Idaho, Inc. (May 1982).
2. C. V. McISAAC and D. G. KEEFER, “TMI-2 Reactor Building Source Term Measurements: Surfaces and Basement Water Sediment,” GEND-042, EG&G Idaho, Inc. (Oct. 1984).
3. T. E. COX, J. T. HORAN and C. V. McISAAC, “Reactor Building Basement Radionuclide Distribution Studies,” GEND-INF-011, Vol. II, EG&G Idaho, Inc. (Oct. 1982).
4. J. K. HARTWELL, J. W. MANDLER, S. W. DUCE and B. G. MOTES, “Characterization of the Three Mile Island Unit-2 Reactor Building Atmosphere Prior to the Reactor Building Purge,” GEND-005, EG&G Idaho, Inc. (May 1981).
5. C. V. McISAAC, “Surface Activity and Radiation Field Measurements of the TMI-2 Reactor Building Gross Decontamination Experiment,” GEND-037, EG&G Idaho, Inc. (Oct. 1983).
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