Refine your search:     
Report No.
 - 
Search Results: Records 1-2 displayed on this page of 2
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Sensitivity analysis of xenon reactivity temperature dependency for HTTR LOFC test by using RELAP5-3D code

Honda, Yuki; Fukaya, Yuji; Nakagawa, Shigeaki; Baker, R. I.*; Sato, Hiroyuki

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.704 - 713, 2016/11

A high-temperature gas-cooled reactor (HTGR) has superior safety characteristics. A loss of forced cooling (LOFC) test using a high-temperature engineering test reactor (HTTR) has been carried out to verify the inherent safety of an HTGR when forced cooling is diminished without reactor scram. In the test, an all-gas circulator was tripped with an initial reactor power of 9 MW and re-criticality was shown. This study focuses on developing a point kinetics method with RELAP5-3D code for an LOFC accident. There is a large temperature difference between the inlet and outlet of the core in an HTGR, and the temperature fluctuation range has been large in several accidents. We analyze the temperature dependency of xenon-135 reactivity and show that the temperature dependency of xenon-135 microscopic absorption cross-section affected the re-criticality time of the LOFC test.

Oral presentation

Development of reactor dynamics method for HTGR under JAEA/INL collaborative research

Honda, Yuki; Sato, Hiroyuki; Nakagawa, Shigeaki; Bayless, P.*; Strydom, G.*; Baker, R. I.*; Gougar, H.*; Sakaba, Nariaki

no journal, , 

The collaborative research between JAEA and Idaho National Laboratory (INL) has been initiated for development and validation of high temperature gas-cooled reactor simulation methods and models. The disclosure data from experiments of High Temperature engineering Test Reactor (HTTR) and High Temperature Test Facility (HTTF), simulation codes and models were exchanged. As one of the collaborative research, it has been focused on construction of reactor dynamics method for High Temperature Gas-cooled Reactor (HTGR) in which transient response of core temperature is complicated with large temperature difference between reactor inlet and reactor outlet. In addition, it has been planned to validate these codes and models with experiment data of Loss of forced cooling (LOFC) test using HTTR. This presentation introduces the outline of the codes and model, and shows the results of LOFC test simulation.

2 (Records 1-2 displayed on this page)
  • 1