Abstract
Reactor Buildings (RBs) for the Next Generation Nuclear Plant (NGNP) High Temperature Gas Cooled Reactor (HTGR) consisting of Reactor Pressure Vessel (RPV) and Steam Generator Vessel (SGV) can be designed as Vented Low Pressure Compartments (VLPCs). In cases of Depressurized Loss of Forced Cooling (D-LOFC) accidents, for instances breaks in the helium pressure boundary, there is a possibility of air ingress into the RPV through the RB vent path. Air ingress into the RPV causes oxidation of the fuel elements and other nuclear-grade graphite components, and its impacts on graphite oxidation are important for assessing safety consequences. In order to predict when oxidation may occur inside the RPV more accurately, close investigation of the helium/air mixture characteristics inside the RB after the D-LOFC event is required. In the present study, RB depressurization characteristics were investigated experimentally on the 1/28 scaled simplified HTGR RB facility. The initial scaled RB pressure was set at 1.2 psig. The natural leak rate of the facility was matched to the conceptual NGNP HTGR RB design criteria: leaking 1 entire volume per day under 1 psig.
| Original language | English |
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| State | Published - 2017 |
| Externally published | Yes |
| Event | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 - Xi'an, Shaanxi, China Duration: Sep 3 2017 → Sep 8 2017 |
Conference
| Conference | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 |
|---|---|
| Country/Territory | China |
| City | Xi'an, Shaanxi |
| Period | 09/3/17 → 09/8/17 |
Funding
This material is based upon work supported by the Department of Energy [National Nuclear Security Administration] under Award Number [DE-NE0008324] in cooperation with AREVA Federal Service LLC (AFS), Ultra Safe Nuclear Corporation (USNC) and AREVA Inc. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. The author would like to acknowledge the work of graduate and undergraduate students such as Mark Silberberg, Chris Fullerton, Stephen King, Andrew Mills, and Mateusz Marciniak.
Keywords
- D-LOFC
- HTGR
- Leak
- Reactor Building