Published May 2014 | Version v1
Journal article

The ATWS analysis of one control rod withdraw out of the HTR-10GT core in addition with bypass valve failure

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Room 207, Building B, Nengkelou, Beijing (China)
  • 2. Institute of Nuclear and New Energy Technology, Tsinghua University, Room 503, Building A, Nengkelou, Beijing (China)

Description

The 10 MW high temperature gas cooled test reactor (HTR-10) has been built in Institute of Nuclear and New Energy Technology (INET) and has been operating successfully since the beginning of 2003. The core outlet temperature of HTR-10 is 700 °C. To verify the technology of gas-turbine direct cycle, at first INET had a plan to increase its core outlet temperature to 750 °C and use a helium gas turbine instead of the steam generator (then the reactor is called HTR-10GT). Though HTR-10 has good intrinsic safety, the design basic accidents and beyond design basic accidents of HTR10-GT must be analyzed according to China's nuclear regulations due to changed operation parameters. THERMIX code system is used to study the ATWS accident of one control rod withdrawal out of the core by a mistake. After a control rod in the side reflector was withdrawn out at a speed of 1 cm/s by a mistake, a positive reactivity was inserted and the reactor power increased and the temperature of the core increased. When the neutron flux of power measuring range exceeded 123% and the core outlet temperature was greater than 800 °C, the reactor should scram. It was supposed that all the control rods in the reflectors had been blocked and the reactor could not scram. Thus the accident went on and the core temperature and the system pressure increased but the reactor shutdown at last because of its natural negative temperature reactivity feedback mechanism, in spite of the failure of bypass valve. The residual heat would be removed out of the core by the cavity cooling system. During the accident sequence the maximum fuel temperature was 1283.3 °C. It was a litter than 1230 °C – the fuel temperature limitation of HTR-10. Now the sphere fuel used in HTR-10GT will also be used in HTR-PM and the temperature limitation will be raised to 1620 °C, so the HTR-10GT is safe during the ATWS of one control rod withdrawal out of the core. The paper also compares the analysis result of HTR10-GT to those of HTR-10. The results shows that the HTR-10GT is still safe during the accident though its operating temperature is higher than HTR-10. The analysis will be helpful to HTR-PM for they have the same outlet temperature of the core

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2013.12.016

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2013.12.016;
PII
S0029-5493(13)00691-2;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
271
Journal Page Range
p. 459-464
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
6. topical meeting on high temperature reactor technology
Acronym
HTR 2012
Dates
28 Oct - 1 Nov 2012
Place
Tokyo (Japan)

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.