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Discussion on the accident behavior and accident management of the HTGR.
- Source :
-
Nuclear Engineering & Design . Apr2020, Vol. 360, pN.PAG-N.PAG. 1p. - Publication Year :
- 2020
-
Abstract
- • This paper introduces accident behavior of typical DBAs and BDBAs of the HTR-PM. • All accidents of the HTR-PM have be divided into several categories, each with similar phenomena or same mitigation measures. • The Extended Emergency Operational Procedures (EEOP) and Beyond design basis accident Additional Mitigation Guideline (BAMG) have been developed for the HTR-PM operators. • This work can provide preliminary reference for the further study on the safety regulation, standards or guidelines for design, operation and accident management of the HTGR. High Temperature Gas-cooled Reactor (HTGR), which plays an important role in the worldwide development of Generation-IV nuclear energy technology, is well-known for the high safety, high efficiency and process heat application. A commercial-scale 200 MWe High Temperature gas-cooled Reactor Pebble-bed Module (HTR-PM) has been designed and is now under construction in Shandong Province, China. Most of the construction and installation work have been finished and the connection to the electric grid will be expected in the end of 2020. In this paper, the reactor behaviors of the HTR-PM during the typical design basis accidents (DBAs) and beyond design basis accidents (BDBAs) have been introduced. In the DBAs, the maximum fuel temperature will never exceed its design limitation of 1620 °C, below which under the design burn-up the "Tristructural-isotropic" (TRISO) coated particles can effectively retain their fission-product inventory. Even in the typical BDBAs with extremely low probability, there is enough time, e.g. several days, to adopt appropriate measures to mitigate the consequence, so that the large release of the radioactive materials would not happen. Accident management is important for the nuclear power plant. Besides, After the Fukushima Dai-ichi nuclear accident, in the worldwide, people are more concerned about the severe accident management of the nuclear power plant, and some standards and guidelines are issued. Based on the accident analyses of the HTR-PM, its accident management is studied and discussed. The designers believe that the accident management procedures can be simplified and no offsite emergency measures are needed for the HTR-PM due to the inherent safety design. Compared to the other types of the nuclear power plant, e.g. the Pressurized-Water Reactor (PWR) power plant, the Severe Accident Management Guideline (SAMG) can be simplified or even unnecessary for the HTR-PM. Above work also can provide reference for the further study on the safety regulations, standards or guidelines for the design, operation and accident management of the HTGR. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00295493
- Volume :
- 360
- Database :
- Academic Search Index
- Journal :
- Nuclear Engineering & Design
- Publication Type :
- Academic Journal
- Accession number :
- 142130235
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2019.110497