Published January 2008 | Version v1
Journal article

Improvement of analysis technology for high temperature gas-cooled reactor by using data obtained in high temperature engineering test reactor

  • 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)

Description

The Very High Temperature Reactor (VHTR) system, which is one of generation IV reactors, is the high temperature gas-cooled reactor (HTGR) with capabilities of hydrogen production and high efficiency electricity generation. The High Temperature Engineering Test Reactor (HTTR) is the first HTGR in Japan. The HTTR achieved full power of 30 MW at a reactor outlet coolant temperature of about 950degC in April, 2004 during the 'rise-to-power tests' confirming the reactor performance. The safety demonstration tests by using the HTTR started from 2002 and are under going to demonstrate inherent safety features of HTGRs. The experimental data obtained in these tests are inevitable to design the VHTR with high cost performance. The analytical models validated through these tests in the HTTR are applicable to precise simulation of an HTGR performance and can contribute to the research and development of the VHTR. (author)

Additional details

Publishing Information

Journal Title
Journal of Power and Energy Systems
Journal Volume
2
Journal Issue
1
Journal Page Range
p. 83-91
ISSN
1881-3062

Conference

Title
15. international conference on nuclear engineering
Acronym
ICONE-15
Dates
22-26 Apr 2007
Place
Nagoya, Aichi (Japan)

Optional Information

Notes
6 refs., 8 figs.