The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities for gas cooled reactor safety studies in June 2009. The programme concluded that actions should be taken to develop an international programme centred on the high-temperature engineering test reactor (HTTR) capabilities and focused on the safety issues identified in TAREF. The Japanese HTTR was identified as a unique resource: it is the only experimental high-temperature gas-cooled reactor (HTGR) facility available in the OECD countries context. It is a graphite moderated, helium cooled reactor that can reach temperature as high as 1600°C in some transient conditions. The LOFC experiments planned to study effects of reactor cavity cooling system (RCCS) performance reduction are highly relevant for safety assessments of advanced reactors such as high temperature reactor (HTR).
The present programme is formulated to investigate safety issues and specifically the anticipated transient without scram (ATWS) with occurrence of reactor re-criticality. The programme is devised to maximise the information deliverables for code validation for one of the most important safety aspects about reactor kinetics, core physics and thermal hydraulics. The test consists of three test cases, run one through three, whose results comparison will provide the incremental performance availability within the vessel cooling system (VCS) range. The experimental programme will provide an experimental database, which will be used to validate code predictive capability and accuracy of models. Phenomena coupled between reactor core physics and thermal hydraulics are to be investigated. The experimental programme and associated analytical activities will help to create a group among NEA member countries which share the need to maintain or improve the technical competence in reactor physics and thermal-hydraulics for safety evaluations of advanced gas cooled nuclear reactor.
The HTTR is a helium-cooled and graphite-moderated HTGR with the thermal power of 30 MW. The reactor outlet coolant temperature is 850˚C at the rated operation and 950˚C in high temperature test operation, respectively. The LOFC test is performed at the rated operation mode. The HTTR consists of reactor core, cooling system, engineered safety systems, instrumentation and control system, etc.
The nuclear instrumentation system of the HTTR is composed of the wide range monitoring system (WRMS) and the power range monitoring system (PRMS). The reactor control system is designed to assure high stability and reasonably damped characteristics against the various disturbances during the operation. The main control system of the HTTR consists of the operational mode selector, the reactor power control and plant control systems. The safety protection system consists of the reactor protection and engineered safety features actuating systems.
The objectives of the proposed project are to conduct integrated large scale test of LOFC in the Japan Atomic Energy Agency (JAEA) HTTR reactor, to examine HTGR safety characteristics in support of regulatory activities, and to provide data useful for code validation and improvement of simulation accuracy. The objective of the experimental programme is to:
These goals will be achieved by using the HTTR to perform three test cases, run one through three, whose results comparison will provide the incremental performance availability within the VCS range. The LOFC test is initiated by tripping all three Helium Gas Circulators (HGCs) of the HTTR while deactivating all reactor reactivity control to disallow reactor scram due to abnormal reduction of primary coolant flow rate. The test falls into ATWS with occurrence of reactor re-criticality. The test will be conducted with and without active function of the VCS.
Czech Republic, France, Germany, Hungary, Republic of Korea, Japan and the USA.
31 March 2011 to 31 March 2014
EUR 3.0 million
Last reviewed: 23 October 2013