NUCLEAR SUPERHEATER FOR A CONTROLLED RECIRCULATION BOILING REACTOR. Interim Feasibility Report
Technical Report
·
OSTI ID:4328169
The objective of this study was to determine and evaluate a means of improving and simplifying the boiling water reactor cycle through use of a nuclear superheater. The steam generated by this two-region, single-core, boiling-superheating reactor is at 825 deg F and 540 psig. The basic design arrangement of the Sioux Falls Power Reactor which appears most feasible at this time incorporates a set of boiling fuel elements surrounding a set of superheater elements, thereby comprising a two-region core. The outer region generates the steam which passes through the irner region to pick up superheat. (W.D.M.)
- Research Organization:
- Allis-Chalmers Mfg. Co. Nuclear Power Div., Milwaukee
- NSA Number:
- NSA-12-012684
- OSTI ID:
- 4328169
- Report Number(s):
- ACNP-5808; AECU-3704
- Country of Publication:
- United States
- Language:
- English
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