Published 2014 | Version v1
Miscellaneous Open

Assessment of Safety Criteria of Indian SFR with respect to International Scenarios

  • 1. Indira Gandhi Centre for Atomic Research (India)
  • 2. BHAVINI, Kalpakkam-603 102 (India)

Description

The core is monitored by functionally diverse sensors: • Neutron detectors to monitor the power and provide signals for safety action by SCRAM on parameters like linear power, period and reactivity; • 3 fast response thermocouples to monitor central fuel subassembly sodium outlet temperature and two thermocouples each within a single thermo-well to monitor other individual SA sodium outlet temperatures; • Thermocouples within thermo-well in each of the two primary sodium pump suction side to monitor the reactor inlet temperature; • Eddy current flow meter to measure the flow delivered by the primary sodium pump, thereby to monitor power to flow ratio; • The pump discharge head and speed are measured and used a trip parameter for pipe rupture and pump seizure respectively; • Failure of fuel is detected by monitoring the cover gas fission product activity and Delayed Neutron Detection (DND) in the primary coolant.

Files

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Part of:
Fourth Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors. Presentations

Additional details

Publishing Information

Imprint Title
Fourth Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors. Presentations
Imprint Pagination
vp.
Journal Page Range
31 p.
Report number
INIS-XA--18K5269

Conference

Title
4. Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors
Dates
10-11 Jun 2014
Place
Vienna (Austria)

Optional Information

Secondary number(s)
IAEA--622-I3-TM-47191