2020 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[1K01-04] Accident Analysis

Mon. Mar 16, 2020 10:45 AM - 11:55 AM Room K (Lecture Bildg. S 2F S-21)

Chair:Chiaki Kino(IAE)

11:15 AM - 11:30 AM

[1K03] Analysis of Halden LOCA Test Using Coupled TRACE/FRAPTRAN Code

*Hiroshi Eguchi1, Kazuharu Fujioka1, Hiroshi Ono1, Hiroaki Uehara2 (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), 2. Japan Atomic Energy Agency)

Keywords:Loss of Coolant Accident (LOCA), TRACE/FRAPTRAN, Halden LOCA test, Fuel Fragmentation, Relocation and Dispersal (FFRD)

As part of the effort to develop an analytical method to evaluate the effect of fuel fragmentation, relocation and dispersal (FFRD) for high burnup fuel on core coolability in a LOCA, simulations of Halden LOCA test using coupled TRACE/FRAPTRAN code were conducted. We present the results using different fuel cladding deformation models.