2023 Fall Meeting

Presentation information

Oral presentation

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

[2O11-14] Advanced Reactor

Thu. Sep 7, 2023 2:45 PM - 3:50 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Ken-ichi Matsuba(JAEA)

2:45 PM - 3:00 PM

[2O11] Analytical Evaluation of loss of forced cooling tests using HTTR

*Sota Nagase1, Kazuhiro Sawa1, Satoru Nagasumi2, Etsuo Ishitsuka2, Kazuhiko Iigaki2 (1. Hokkaido Univ., 2. JAEA)

Keywords:HTGR, HTTR, LOFC, TAC/BLOOST

The loss of forced cooling (LOFC) tests have been carried out by Japan Atomic Energy Agency (JAEA) using the High Temperature engineering Test Reactor (HTTR). In order to demonstrate safety feature of the High Temperature Gas-cooled Reactors, helium gas is decreased to zero without reactor power control by control rods.
In this study, reactor power and reactivity are evaluated by changing coolant flow rate in the LOFC tests. A reactor kinetics analysis code called the TAC/BLOOST code is used in the analysis.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password