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"Argonaut" - A Generalized Reactor Facility for Nuclear Technology Training and Research (Interim Report)

1956/03/01 by D.H. Lennox, Bernard I. Spinrad · 1 citation
Materials Science · Physics and Astronomy · Engineering · Chemistry · #Graphite, nuclear technology, radiation studies #Nuclear Physics and Applications #Nuclear reactor physics and engineering #Nuclear engineering #Control rod #Electromagnetic shielding #Rod #Neutron #Graphite #Materials science #Neutron temperature #Research reactor #Liquid nitrogen #Neutron poison #Enriched uranium #Borax #Neutron moderator #Nuclear physics #Uranium #Composite material #Engineering #Physics #Chemistry #Neutron cross section

paper · doi:10.2172/4370769

openalex publication_date 1956/03/01 · openalex created_date 2025/10/10 · openalex updated_date 2026/06/26

Abstract

The great expansion of nuclear technology which is expected within the next decade requires new tools, both for education and for the performance of tests on the physics design of the systems to be studied. Presently existing research reactors were not designed to meet these needs. Their high power levels do not permit flexibility of installation and limit the usefulness of the reactors a s measuring tools (for example, for danger coefficient and pile oscillation studies). Therefore, such reactors as CP-5, MTR, LITR, and the Brookhaven Reactor have become basically high-level neutron sources for experiments in pure science and radioactive engineering.

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