Boiling water neutronic reactor incorporating a process inherent

Induced nuclear reactions: processes – systems – and elements – With control of reactor – By movement of control element or by release of neutron...

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376282, 376247, G21C 706

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active

046666540

ABSTRACT:
A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

REFERENCES:
patent: 4204909 (1980-05-01), Giuggio et al.
patent: 4363780 (1982-12-01), Hannerz
patent: 4483192 (1984-11-01), Wachter
patent: 4526742 (1985-07-01), Hannerz
K. Hannerz, "Applying Pius to Power Generation: The Secure-PLWR", Power Plant Design, 12/83, pp. 41-46.
Asea-Atom-Always in the Forefront, "The Ultimate in BWR Design Simplicity-The Key to Improvement Performance", Nuclear News, Nov. 1983, pp. 30-31.
L. Wann, "Congress to Bet Millions `Meltdown Proof` Reactors Can Save Nuclear Industry", Chattanooga Times, Feb. 1984.
"PIUS Gets Cautious But Hopeful Reception at NRC", Nucleonics Week, Oct. 13, 1983, p. 3.
K. Hannerz, "Towards Intrinsically Safe Light Water Reactors", Institute for Energy Analysis, Oak Ridge Associated Universities ORAU/IEA-31-2(M)-Rev., Research Memorandum, Jul. 1983.

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