Category Archives: ANNEX III. AHWR. Bhabha Atomic Research Centre, India

The integral reactor coolant system

The IRIS reactor vessel (RV) [1] houses not only the nuclear fuel and control rods, but also all the major reactor coolant system (RCS) components (see Fig. XVI-1): eight small, spool type, reactor coolant pumps (RCPs); eight modular, helical coil, once through steam generators (SGs); a pressurizer located in the RV upper head; the control rod drive mechanisms (CRDMs); and, […]

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Accumulators (ACC)

The accumulators are similar to those found in conventional PWRs. They are large spherical tanks approximately three-quarters filled with cold borated water and pre-pressurized with nitrogen. The accumulator outlet line is connected to the DVI line. A pair of check valves prevents injection flow during normal operating conditions. When system pressure drops below the accumulator pressure (plus the check valve […]

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Description of passive residual heat removal system via steam generator

A passive residual heat removal system (see Figure XIII-3) is included in the design to remove heat from the reactor plant. The PHRS is designed in case of a station blackout including the loss of emergency power supply. The removal of residual heat should be provided without damage to the reactor core and the primary system boundary for an unlimited […]

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Beyond design basis accidents

XIX-4.5.1. Severe accidents Compared to the standard PWR, safety is improved by the elimination of initiating events based on a specific design, as mentioned previously (optimum between safety, economy and human interface): large breaks on the primary circuit, reactivity insertion accident by rod ejection. However, the hypothetical case of a core meltdown is manageable in the following manner:

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