Dynamic simulation of Indian PHWRs
Description
System process dynamics of a specific nuclear power plant plays an important role in designing and tuning of different control systems. The control systems are designed to make the plant tolerant to expected and unexpected transients to avoid outages. Corrective action continues till the process variables are brought back to the normal operating condition. A design objective has been to make the intervention of the shutdown systems unnecessary in all cases. To evaluate and test new features such as design modification, new operating procedures, optimization of process parameters and controllers as compared to the existing procedures, an integrated process dynamic simulation model is required. The process dynamic simulation is basically devised to analyse anticipated plant operational transients and also some of the safety related transients. In the background of an operator-training simulator, an integrated fast executable process dynamic model is used. But one needs a versatile and an accurate process model to analyse the unusual occurrences reported from the operating plant sites for mitigating the consequences. Keeping all the above mentioned points in mind, mathematical models for all the major components and sub-systems of the 220 MWe and the 500 MWe PHWR were developed based on the conservation equations of mass, momentum, energy and equation of state. All the associated control systems are also modeled. The PHT system includes the reactor store with nuclear fuel, primary circulating pump (PCP), primary heat transport (PHT) system pressure controller with feed/bleed system and pressuriser (Surge Tank). The secondary system includes mainly the steam generators (SGs) process, the SG level and pressure controllers, apart from the various steam cycle components. All these models are integrated together to form the plant transient analysis computer code. Extensive transient analysis studies have been carried out using these codes, to check the various design parameters and controller settings. The paper deals with the details of the various plant transient analysis. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- First national conference on nuclear reactor technology
- Imprint Pagination
- 421 p.
- Journal Page Range
- p. 232-246
Conference
- Title
- 1. nuclear reactor safety
- Acronym
- NRT-1
- Dates
- 25-27 Nov 2002
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34011331
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN BASIS ACCIDENTS; HEAT TRANSFER; NUCLEAR POWER PLANTS; PHWR TYPE REACTORS; POWER RANGE 100-1000 MW; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; SCRAM; SPECIFICATIONS; STEAM GENERATORS; TRANSIENTS; TURBINES
- Descriptors DEC
- ACCIDENTS; BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MACHINERY; MEGAWATT POWER RANGE; NUCLEAR FACILITIES; POWER PLANTS; POWER RANGE; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL POWER PLANTS; TURBOMACHINERY; VAPOR GENERATORS
Optional Information
- Notes
- 17 refs., 14 figs., 1 tab.