Sodium Graphite Reactors
Author | : Chauncey Starr |
Publisher | : |
Total Pages | : 312 |
Release | : 1958 |
Genre | : Sodium graphite reactors |
ISBN | : |
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Author | : Chauncey Starr |
Publisher | : |
Total Pages | : 312 |
Release | : 1958 |
Genre | : Sodium graphite reactors |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1960 |
Genre | : |
ISBN | : |
A description is given of the Advanced Sodium Graphite Reactor Power Plant, including the reactor, heat transfer systems, generatirg plant, control systems, and the economics of producing 256 Mw(e). The safety of this design is due to its unusually low operating pressure, absence of chemically incompatible materials in the core, and excellent stability under atatic and dynamic conditions. The reactor is being constructed at Hallam, Nebraska, at a probable cost of 0 to 0/kw, exclusive of the first core costs. The 151 fuel elements of uranium carbide are enriched to 2.75 at.% U235 and clad in stainless steel. The average thermal neutron flux in the fuel is 8 x 1013 n/cm2sec. (B.O.G.).
Author | : |
Publisher | : |
Total Pages | : 68 |
Release | : 1955 |
Genre | : Liability for nuclear damages |
ISBN | : |
Author | : B. R. Hayward |
Publisher | : |
Total Pages | : 52 |
Release | : 1959 |
Genre | : Sodium graphite reactors |
ISBN | : |
Author | : H. H. Cappel |
Publisher | : |
Total Pages | : 60 |
Release | : 1961 |
Genre | : Nuclear reactor kinetics |
ISBN | : |
Author | : Atomics International, California |
Publisher | : |
Total Pages | : 22 |
Release | : 1958* |
Genre | : |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1958 |
Genre | : |
ISBN | : |
The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U235) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors are discussed. Burn-up limitations encountered for metallic fuel in the SGR temperature range indicate UO2 the more desirable choice. The estimated cost of electrical energy associated with the UO2 fuel is given. (auth).