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Reactor Design & Development Group
Reactor Engineering Division (Applied Engineering and R&D Activities)

Expertise in 

  • Design, development and analysis of mechanical components 

  • Thermal hydraulics 

  • Vibration diagnostics

  • Repair technology

  • Process instrumentation

Meets the requirements of DAE and non – DAE Units

Division is equipped with strong infrastructure and adequately supported with experimental facilities and test loops for short and long term testing of components under simulated conditions

  • Large number of reactor process equipments/components evaluated

  • Variety of base line data on the process variables and performance parameters generated through the operation of theses test facilities

  • Developed various codes for the verification of design analysis

Significant work carried out by the division in the design, development and operation of the nuclear power and research reactors and other nuclear facilities.

Major Activities

  • Design, Analysis and Engineering development on Advanced Heavy Water Reactor (AHWR) 

  • A Natural Circulation Loop set up to study the natural circulation phenomena and its stability in AHWR 

  • Full size fuel clusters in alternate design configurations have been assembled and subjected to prolonged endurance tests under simulated flow conditions as a part of the development of the AHWR fuel 

  • Optimisation of thermal hydraulic design of AHWR.

  • Design of scaled up models for performance evaluation of some of the components.

Around two tonnes of MOX fuel loaded in reactors at Tarapur. Utilisation of thorium as fuel is one of the major milestones in our nuclear power programme and work in this direction has also been initiated by flux flattening in Kakrapar reactor.

Commissioning of the Facility for Integral System Behavior Experiments (FISBE). This facility permits experimental simulation of accident scenarios and operational transients in PHWRs.

Some of the other major experimental facilities include 3 MW Boiling water loop, High Temperature Loop, High Flow Test Facility and Flow Test Facility. 

Carried out performance and type testing of primary heat transport system main pumps (3600 HP) of PHWRs, bellow seal valves, grayloc couplings of coolant channels etc. Investigations to establish adequacy of thermosyphon performance of NAPS-1 reactor were also carried out at site.

Set up a Vibration Laboratory and has developed and implemented the techniques for root cause identification of premature failure of equipment, for diagnostic monitoring and seismic qualification of equipments

Non Intrusive Vibration diagnostic technique (NIVDT) has been developed and successfully implemented for identifying coolant channels having pressure tube-calandria tube contact in PHWRs.

Vibration Diagnostics and trouble-shooting for structures and rotating machineries

  • Turbo-generator sets and process water pumps of nuclear power plants. 

  • In-situ vibration diagnostic monitoring for turbine blades in nuclear power plants and motor current signature analysis for conventional power plants of NTPC. 

  • Root cause identification of vibrations for building structure of Rashtriya Chemicals and Fertilisers (RCF) and Cancer Research Institute (CRI). 

  • Detection of turbine blade vibration and monitoring of crack in vertical pump shaft for M/s. I. S. Tec, Germany.

  • RED Expertise utilized by German Railways for development of an on-board vibration monitoring system for high speed trains.

Development of various types and sizes of rolled joints between Zircaloy/Zr-Niobium - Stainless Steel (SS) and between SS-SS 

  • For coolant channel components and secondary shut down systems of PHWRs. 

  • Production of rolled joints of secondary systems of PHWR and of Dhruva reactor

  • Beam tube rolled joint of Kamini Reactor developed and rolled at site.

Repair Technology Development for PHWR components - RED Expertise. 

  • Developing computer codes SCAPCA (for creep sag analysis of coolant channels), HYCON (for estimation of hydrogen concentration), BLIST, CEAL etc for life assessment of the components and designing the tools and systems for in-service repair and remote inspection.

  • Design and development of Integrated Garter Spring Repositioning System (INGRES), Sliver Sample Scraping Tool (SSST), Dry channel Visual Inspection System (DRYVIS) for coolant channel life extension and inspection 

  • Experimental & theoretical studies are pursued in the form of collaborative work with IAEA and other academic Institutions. RED participated in IAEA Coordinated Research Programmes on thermophysical properties and thermohydraulic relationships. Engineering consultancy has been offered for development of hydrogen mitigation technique and development and implementation of chemical decontamination system.