TRAC analysis of design basis events for the accelerator production of tritium target/blanket | Zendy

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TRAC analysis of design basis events for the accelerator production of tritium target/blanket

Author(s) -

Jay Lin,

Jay S. Elson

Publication year - 1997

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/510430

Subject(s) - trac , nuclear engineering , decay heat , blanket , transient (computer programming) , coolant , water cooling , environmental science , scram , nuclear physics , materials science , physics , mechanical engineering , engineering , computer science , composite material , operating system

A two-loop primary cooling system with a residual heat removal system was designed to mitigate the heat generated in the tungsten neutron source rods inside the rungs of the ladders and the shell of the rungs. The Transient Reactor Analysis Code (TRAC) was used to analyze the thermal-hydraulic behavior of the primary cooling system during a pump coastdown transient; a cold-leg, large-break loss-of-coolant accident (LBLOCA); a hot-leg LBLOCA; and a target downcomer LBLOCA. The TRAC analysis results showed that the heat generated in the tungsten neutron source rods can be mitigated by the primary cooling system for the pump coastdown transient and all the LBLOCAs except the target downcomer LBLOCA. For the target downcomer LBLOCA, a cavity flood system is required to fill the cavity with water at a level above the large fixed headers

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