MELCOR ex-vessel LOCA simulations for ITER

Author

Gaeta, Michael J. ; Merrill, Brad J. ; Bartels, Hans-Werner ; Topilski, Leonid

Author_Institution

Lockheed Martin Idaho Technol. Co., Idaho Nat. Eng. Lab., Idaho Falls, ID, USA

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

309

Abstract

Ex-vessel loss-of-coolant-accident (LOCA) simulations for the International Thermonuclear Experimental Reactor (ITER) were performed using the MELCOR code. The main goals of this work were to estimate the ultimate pressurization of the heat transport system (HTS) vault in order to gauge the potential for stack releases and to estimate the total amount of hydrogen generated during a design basis ex-vessel LOCA. Simulation results indicated that the amount of hydrogen produced in each transient was below the flammability limit for the plasma chamber. In addition, only moderate pressurization of the HTS vault indicated a very small potential for releases through the stack

Keywords

accidents; cooling; fusion reactor design; fusion reactor operation; fusion reactor reaction chamber; fusion reactor safety; nuclear engineering computing; H; ITER; International Thermonuclear Experimental Reactor; MELCOR code; MELCOR ex-vessel LOCA simulations; ex-vessel loss-of-coolant-accident; flammability limit; fusion reactor; heat transport system pressurization; plasma chamber; stack releases; transient; Chemicals; Coolants; Cooling; High temperature superconductors; Hydrogen; Inductors; Plasma simulation; Plasma temperature; Solid modeling; Vacuum systems;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534229

Filename

534229