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Title: Control of reactor coolant flow path during reactor decay heat removal

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool intomore » the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.« less
Authors:
 [1]
  1. (Los Gatos, CA)
Publication Date:
OSTI Identifier:
866703
Report Number(s):
US 4767594
DOE Contract Number:
AC03-85NE37937
Resource Type:
Patent
Research Org:
GENERAL ELECTRIC CO
Country of Publication:
United States
Language:
English
Subject:
control; reactor; coolant; flow; path; reactor; decay; heat; removal; improved; reactor; vessel; auxiliary; cooling; sodium; cooled; nuclear; reactor; disclosed; sodium; cooled; nuclear; reactor; type; reactor; vessel; liner; separating; reactor; hot; pool; upstream; intermediate; heat; exchanger; reactor; cold; pool; downstream; intermediate; heat; exchanger; improvement; flow; path; reactor; vessel; liner; flow; gap; dissipates; core; heat; reactor; vessel; containment; vessel; responsive; casualty; including; loss; normal; heat; removal; paths; associated; shutdown; main; coolant; liquid; sodium; pumps; normal; operation; reactor; vessel; cold; pool; inlet; suction; coolant; liquid; sodium; pumps; pumps; electromagnetic; variety; pumps; discharge; core; reactor; hot; pool; intermediate; heat; exchanger; heat; generated; reactor; core; discharged; outlet; heat; exchanger; sodium; returned; reactor; cold; pool; improvement; placing; jet; pump; reactor; vessel; liner; flow; gap; pumping; flow; liquid; sodium; pressure; cold; pool; hot; pool; jet; pump; pressure; driving; stream; diverted; pressure; reactor; pumps; normal; operation; jet; pumps; supplement; normal; reactor; pressure; differential; pressure; cold; pool; hot; pool; occurrence; casualty; involving; loss; coolant; pump; pressure; immediate; cooling; circuit; established; flow; sodium; jet; pumps; reactor; vessel; hot; pool; reactor; vessel; cold; pool; cooling; circuit; flow; reactor; vessel; liner; flow; gap; immediate; reactor; vessel; wall; containment; vessel; optimum; immediate; discharge; residual; reactor; heat; occurs; vessel liner; vessel liner; vessel liner; vessel liner; vessel wall; decay heat; reactor coolant; normal operation; normal operation; reactor pressure; containment vessel; containment vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; reactor vessel; heat exchange; heat exchange; heat exchange; heat exchange; nuclear reactor; nuclear reactor; heat exchanger; heat exchanger; heat exchanger; heat exchanger; reactor core; pressure differential; flow path; flow path; liquid sodium; liquid sodium; liquid sodium; coolant flow; heat removal; heat removal; heat generated; cooled nuclear; cooled nuclear; hot pool; hot pool; hot pool; hot pool; hot pool; reactor heat; auxiliary cooling; jet pump; jet pump; jet pump; jet pump; coolant liquid; coolant liquid; normal reactor; cold pool; cold pool; cold pool; cold pool; cold pool; cold pool; cooling circuit; cooling circuit; sodium pumps; sodium pumps; vessel auxiliary; sodium cooled; sodium cooled; coolant pump; intermediate heat; intermediate heat; intermediate heat; reactor pump; core heat; improved reactor; sodium pump; sodium pump /376/976/