TY - JOUR
T1 - An endothermic chemical process facility coupled to a high temperature reactor. Part I
T2 - Proposed accident scenarios within the chemical plant
AU - Brown, Nicholas R.
AU - Seker, Volkan
AU - Revankar, Shripad T.
AU - Downar, Thomas J.
N1 - Funding Information:
One author (S.T.R.) was partially supported by WCU (World Class University) program through the National Research Foundation of Korea funded by the Ministry of Education, Science and Technology ( R31 - 30005 ).
Funding Information:
Portions of this research were performed under an appointment to the U.S. Department of Homeland Security (DHS) Scholarship and Fellowship Program, administered by the Oak Ridge Institute for Science and Education (ORISE). All opinions in this paper are the author's and do not necessarily reflect the policies or views of the DHS, DOE, or ORISE.
Funding Information:
Portions of this research were sponsored by the Bilsland Fellowship at Purdue University.
PY - 2012/5
Y1 - 2012/5
N2 - Hydrogen generation using a high temperature nuclear reactor as a thermal driving vector is a promising future option for energy carrier production. In this scheme, the heat from the nuclear reactor drives an endothermic water-splitting plant, via coupling, through an intermediate heat exchanger. Quantitative study of the possible operational or accident events within the coupled plant is largely absent from the literature. In this paper, seven unique case studies are proposed based on a thorough review of possible events. The case studies are: (1) feed flow failure from one section of the chemical plant to another with an accompanying parametric study of the temperature in an individual reaction chamber, (2) product flow failure (recycle) within the chemical plant, (3) rupture or explosion within the chemical plant, (4) nuclear reactor helium inlet overcooling due to a process holding tank failure, (5) helium inlet overcooling as an anticipated transient without emergency nuclear reactor shutdown, (6) total failure of the chemical plant, (7) control rod insertion in the nuclear reactor. The qualitative parameters of each case study are outlined as well as the basis in literature. A previously published modeling scheme is described and adapted for application as a simulation platform for these transient events. The results of the quantitative case studies are described within part II of this paper.
AB - Hydrogen generation using a high temperature nuclear reactor as a thermal driving vector is a promising future option for energy carrier production. In this scheme, the heat from the nuclear reactor drives an endothermic water-splitting plant, via coupling, through an intermediate heat exchanger. Quantitative study of the possible operational or accident events within the coupled plant is largely absent from the literature. In this paper, seven unique case studies are proposed based on a thorough review of possible events. The case studies are: (1) feed flow failure from one section of the chemical plant to another with an accompanying parametric study of the temperature in an individual reaction chamber, (2) product flow failure (recycle) within the chemical plant, (3) rupture or explosion within the chemical plant, (4) nuclear reactor helium inlet overcooling due to a process holding tank failure, (5) helium inlet overcooling as an anticipated transient without emergency nuclear reactor shutdown, (6) total failure of the chemical plant, (7) control rod insertion in the nuclear reactor. The qualitative parameters of each case study are outlined as well as the basis in literature. A previously published modeling scheme is described and adapted for application as a simulation platform for these transient events. The results of the quantitative case studies are described within part II of this paper.
UR - http://www.scopus.com/inward/record.url?scp=84859213306&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84859213306&partnerID=8YFLogxK
U2 - 10.1016/j.nucengdes.2011.12.027
DO - 10.1016/j.nucengdes.2011.12.027
M3 - Article
AN - SCOPUS:84859213306
SN - 0029-5493
VL - 246
SP - 256
EP - 265
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
ER -