Physics design aspects of the 100 MW thermal research reactor in Trombay

Technical Report · Mon Jan 01 04:00:00 EST 1973

OSTI ID:4306760

Veeraraghavan, N; Sankaranarayanan, S; Paul, O P.K.; Sen Gupta, S N

From symposium on nuclear science and engineering; Bombay, India (13 Mar 1973). The physics design analysis employed for the choice of an optimum core for the 100 MW thermal research reactor is presented. The design lays emphasis to achieve as maximum a neutron flux in the core as feasible for minimum heavy water and uranium inventories in the reactor vessel, while meeting the excess reactivity requirements for operational and other loads at rated reactor power. A computer program FLOEST incorporating the coupled aspects of heat transfer-core size and reactivity is developed for such optimization studies. The reactor is to be controlled by 16 to 18 stainless steel control rods. Calculational methods for the in-sequence reactivity-worths of these control/ shut-off rods and their effect on the power distribution of a fully loaded core configuration are presented. Shut-down margin aspects of the control system are discussed. Measures for emergency shutdown of the reactor are studied. (auth)

• Research Organization: Bhabha Atomic Research Centre, Bombay (India)
• NSA Number: NSA-29-031411
• OSTI ID: 4306760
• Report Number(s): INIS-mf--1162
• Country of Publication: India
• Language: English

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