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Emergency cooling systems

Provision of emergency cooling systems for reactors, where heat continues to be generated after shut-down for instance, in some polymerisation systems. [Pg.370]

The process unit has many loss control features. The plant has a diesel emergency power generator with an emergency cooling system. The plant is also under computer control with emergency shutdown based on redundant inputs. Vacuum is always broken with nitrogen. The process has complete, written, and up-to-date operating instructions. A reactive chemicals review was completed recently. The process has several interlocks to prevent polymerization. [Pg.468]

The TNR is an important feature if an emergency cooling system has to cope with an imminent runaway reaction it must become efficient in a time shorter than TNR. [Pg.55]

Emergency cooling systems to slow reaction and/or reduce pressure buildup ... [Pg.12]

An experiment to find out how long power was generated as the reactor unit was shut down was authorized. But, automatic shut-down mechanisms were blocked that may have come into operation at low capacity levels. These included the reactor s emergency cooling system and its low water level safeguard. Extra pumps were also turned to raise the amount of steam going to the generator. These pumps were over the allowable level. [Pg.231]

In nuclear installations the so-called design basis accidents are used for this purpose [19]. For example, the complete failure of the main coolant pipe of a reactor ( 2-F — rupture because the entire cross section is open on both sides) or the failure of the electric supply [19]. The design basis accidents serve to determine the type and dimensions (e.g. capacity, temperatures, cooling power...) of the corresponding safety systems, for example the emergency cooling system for counteracting the breach of the main coolant pipe. [Pg.118]

Example 9.26 Unavailability of an emergency cooling system pump... [Pg.377]

After the start of the emergency cooling system of a nuclear power station the radiation level drops to a value which permits a repair of the emergency cooling pump only after 48 h. It is assumed that the pump starts on demand. For its failure during operation a rate of Ji, = 42 x 10 h applies the average time for repair amounts to = 20 h. [Pg.377]

The cooling water supply to a condenser was blocked by pebbles and the operator did not turn on the emergency cooling system to the reactor jacket. However, when the runaway started the reactor contents were safely emptied to a dump tank. [Pg.186]

Residual Heat Removal (RHR) System 5.6 Emergency Cooling System... [Pg.65]

Compared with the set of safety systems subsequently considered essential, an emergency cooling system was missing as decay heat was practically absent after shut down, and there was no containment system (except for a curtain ) provided as the amount of fission products was not significant. [Pg.2]

US Code of Federal Regulations (2000b) Part 50.46 Acceptance Criteria for Emergency Cooling Systems for Light Water Nuclear Power Reactors , US Government. [Pg.10]

The emergency cooling systems are both passive ones (that is those practically without moving components, such as pumps) and active ones. By way of examples. Figure 3-1 shows a passive system (accumulators, AC, kept under pressure by compressed nitrogen) and an active system (I). [Pg.18]

The core emergency cooling system is placed in Class 2, as its failure doesn t cause directly and necessarily an accident. [Pg.118]

The compressed air system which supports the emergency cooling systems is in Class 3 as it is considered a normal, not highly stressed system. [Pg.118]

An improvement of the emergency cooling system in case of earthquake. [Pg.29]

The question whether, e.g., the primary products in chain with A = 70 are mainly nickel (Z = 28, N = 42) or cobalt (Z = 27, iV= 43) is decisive for the question whether the closed shell with Z = 28 plays a role. The lengths of the P-decay chains are important for the safety of reactors, as P decay produces heat even after the shutdown of a reactor and this heat has to be carried off even in case of an accident. An emergency cooling system has to be designed accordingly. Prompt neutron emission competes with P decay. The number of prompt neutrons emitted determines the possibility for a chain reaction. [Pg.263]

As in the case of the emergency cooling systems, the safety-related auxiliary electrical power supply equipment is divided into four independent and physically separated parts, or subdivisions, and the reactor protection system operates on a 2-out-of-4 logic for signal transmission and actuation. [Pg.51]


See other pages where Emergency cooling systems is mentioned: [Pg.239]    [Pg.161]    [Pg.311]    [Pg.115]    [Pg.10]    [Pg.250]    [Pg.214]    [Pg.17]    [Pg.261]    [Pg.207]    [Pg.10]    [Pg.11]    [Pg.10]    [Pg.2575]    [Pg.54]    [Pg.551]    [Pg.552]    [Pg.33]    [Pg.52]    [Pg.21]    [Pg.23]    [Pg.415]    [Pg.34]    [Pg.51]    [Pg.130]    [Pg.243]    [Pg.2]    [Pg.446]   
See also in sourсe #XX -- [ Pg.55 , Pg.261 ]




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Cooling systems

Emergency systems

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