• Design & detailed engineering of structures, systems and components for Advanced Heavy Water Reactor (AHWR)
• Preparation of documents for regulatory / statutory approval and financial sanction of AHWR
• Pre-project activities and infrastructure development at AHWR site
• Research & Development (R&D) pertaining to Mechanical, Instrumentation and Process Systems of AHWR
• Development of innovative instrumentation sensors and systems for AHWR
• Design & implementation of I&C systems for reactor related experimental facilities
• Research & Development (R&D) for other power reactors (PHWR, PWR, HTR) and research reactors
• Technological support for non-reactor applications
1. Thermal and structural analysis of an RF LINAC cavity has been performed to assess the deflection in cavity due to temperature gradients.
\r\n2. A Modification has been proposed in the end flange of LINAC to enhance the allowable RF power fed to the cavity,
\r\n3. Thermal and structural analysis has been performed with proposed modification as well.
1. Probable Maximum Tropical Storm (PMTC) parameters for Western coast have been determined by probabilistic analysis.
\r\n2. Design basis flood level for the site has been estimated based on the surge caused by PMTC.
\r\n3. Beyond Design Basis Flood Level has also been estimated for the site based on AERB recommendation.
\r\n4. Various protection wall profiles have been studied and optimum design has been selected. Finished Grade Level can be reduced by incorporating protection wall around the plant.
• Design, Analyses & Seismic Qualification as per ASME BVC requirement has been carried out(rev P0) (around 30 No’s)
\r\n• 3D-Modelling & Associative Design Drawing(rev P0) for the aforementioned Pressure Vessel & Components have been carried out.
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Layout Design of Seven Nuclear Island Buildings (Reactor Building, Service Building, Control Building, Backup Control Building, Station Auxilary Building, Fuel Building, DG Building) have been carried out(rev P0).Similarly, Layout of other seven following buildings of AHWR Plant has been carried out (rev P0).
\r\n1. Administrative Building
\r\n2. Administrative Service Building
\r\n3. Waste Management Plant Building
\r\n4. Central Alarm System Building
\r\n5. Fire Water Reservoir & Pump House
\r\n6. Domestic Water Reservoir & Pump House
\r\n7. Diesel Oil Storage Area
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Layout Design of Seven Nuclear Island Buildings (Reactor Building, Service Building, Control Building, Backup Control Building, Station Auxilary Building, Fuel Building, DG Building) have been carried out(rev P0).Similarly, Layout of other seven following buildings of AHWR Plant has been carried out (rev P0).
\r\n1. Administrative Building
\r\n2. Administrative Service Building
\r\n3. Waste Management Plant Building
\r\n4. Central Alarm System Building
\r\n5. Fire Water Reservoir & Pump House
\r\n6. Domestic Water Reservoir & Pump House
\r\n7. Diesel Oil Storage Area
\r\n
Layout Design of Seven Nuclear Island Buildings (Reactor Building, Service Building, Control Building, Backup Control Building, Station Auxilary Building, Fuel Building, DG Building) have been carried out(rev P0).Similarly, Layout of other seven following buildings of AHWR Plant has been carried out (rev P0).
\r\n1. Administrative Building
\r\n2. Administrative Service Building
\r\n3. Waste Management Plant Building
\r\n4. Central Alarm System Building
\r\n5. Fire Water Reservoir & Pump House
\r\n6. Domestic Water Reservoir & Pump House
\r\n7. Diesel Oil Storage Area
\r\n
Admittance Probe sensor for real time Void measurements was developed for high pressure and temperature Steam-Water conditions of AHWR. The sensor output is linear and is able to predict the void fraction in wide range of operation. This sensor causes no pressure drop in the system.
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Sensor for transient void measurements, void distribution and visualization is very important for sub-channel thermal hydraulic analysis related to nuclear reactor safety. Hence Development of Wire Mesh type sensor for high speed measurement and qualification in Air-Water Experimental set-up were carried out. WMS for Sub-channel geometry was designed and tested in AHWR Fuel Sub-Channel Set Up. Image processing of experimental data for void profile visualization were carried out.
Validity Studies were carried out using Experimental investigation and CFD Simulation for the following system of AHWR:
\r\n1. Moderator Flow Distribution in Calandria
\r\n2. Liquid Poison Injection & Distribution in Calandria
\r\n3. Passive Containment Cooling System
\r\n4. Passive Containment Isolation System
\r\n5. Reactive Mechanism Cooling System
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Sensors for measurement of liquid film thickness and film flow rate during annular flow regime in two-phase flow process are essential for dry out prediction in AHWR rod cluster. Hence Conductance based Film Thickness Sensor and Film Extraction by sinters & flow rate measurement by novel miniature integral orifice were developed. Experiments carried out in Air-Water Annular Flow Facility successfully. High temp Conductance probe and Film extraction by SS Sinters were commissioned in CHF & Instability Loop for Steam-Water studies. Experiments are in progress.
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Bi-directional ventury flow meter has been developed and calibrated with primary instruments working on first principle.The flow meter is tested for various transients and accidental scenarios of AHWR in full scale experimental test facility.
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CHF data was successfully generated in one-sixth sector of AHWR Fuel Cluster at Reactor operating conditions using surface mounted miniature MI thermocouples (T/Cs) technique. The T/Cs were closely spaced near the high quality zone for collecting CHF data. It is observed that CHF occurred at the exit of the T/S. Around 50 CHF data were generated successfully. This measurement helped in obtaining AHWR Critical Power and Thermal Margin.
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Engineering Design Centre having Computational Infrastructure and software for Plant Design & Plant Life Cycle Management has been established at NRB- Building Anushaktinagar for Plant Design & Virtual prototyping of plant component.
AHWR Plant
