The Nuclear Safety Research Reactor (NSRR) in Japan

Author:

Ishikawa Michio,Inabe Teruo

Publisher

Springer US

Reference15 articles.

1. Dietrich, J. R., “Experimental Investigation of the Self-limitation of Power Driving Reactivity Transients in a Sub cooled, Water-moderated Reactor,” USAEC Report ANL-5323, Argonne National Laboratory, 1954.

2. Spano, A. H., Barry, J. E., Stephan, L. A. and Young, J. C., “Self-limiting Power Excursion Tests of a Water-moderated Low-enrichment U02 Core in SPERT-1,” USAEC Report IDO-16751, Phillips Petroleum Co., 1962.

3. “IDO Report on the Nuclear Incident at the SL-1 Reactor, January 3, 1961, at the National Reactor Testing Station,” USAEC Report IDO-19302, Idaho Operations Office, 1962.

4. Miller, R. W., Sola, A. and McCardell, R. K., “Report of the SPERT-1 Destructive Test Program on an Aluminum, Plate-Type, Water-rmoderated Reactor,” USAEC Report IDO-16883, Phillips Petroleum Co., 1964.

5. Neal, W. J. (Editor), “Safety Analysis Report SNAPTRAN 2/10A-1 and -2 Safety Tests,” USAEC Report IDO-17076, Phillips Petroleum Co., 1965.

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