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Both involve loss of forced coolant to the core, except the latter involves a pressure loss in the main coolant loop.
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The simulation domain reproduces with some simplification the entire primary coolant loop.
A number of accidents leading to the release of a secondary phase into the primary coolant loop are investigated.
In this paper results are presented from thermal-hydraulic analyses of two postulated transients in the divertor cooling loop system, (i) trip of the main coolant pump in the divertor primary heat transport system, and (ii) loss of heat sink in the divertor cooling system; trip of the secondary side pump.
Primary and other loops in multiple coolant loop systems in nuclear power plants can be modeled in nuclear system codes, such as Reactor Excursion and Leak Analysis Program (RELAP5), COBRA-TRAC, TRACE, and ATHLET, for the interaction and feedback effects between the coolant loops.
Non-uniform and asymmetric loop flow mixing in the reactor vessel has been observed in the event of symmetric main coolant pump operation.
Pressure in the coolant loop was also holding, another indicator that the problem had been resolved.
Freon, the main coolant used in the enrichment plants, is steadily leaking away.
In December 1995, a coolant loop leaked more than 700 kilograms of molten sodium, releasing toxic fumes and damaging the plant.
Liquid sodium is the main coolant in Fast Breeder Nuclear Reactor.
In the breeder region, part of the produced tritium can permeate into the coolant loop, from the coolant into the steam generator and thus reach the environment.
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