Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.

Gelbard, Fred ; Oh, Seungmin (Purdue University, West Lafayette, IN) ; Rodriguez, Salvador B. ; Revankar, Shripad T. (Purdue University, West Lafayette, IN) ; Gauntt, Randall O. ; Cole, Randall K., Jr. ; Espinosa, Flor (University of New Mexico, Albuquerque, NM

关键词: ANALYTICAL SOLUTION;    CHEMISTRY;    DESIGN;    FLOWSHEETS;    HYDROGEN;    HYDROGEN PRODUCTION;    IODINE;    KINETICS;    NUCLEAR POWER;    PRODUCTION;    REACTORS;    SAFETY;    SULFUR;    TRANSIENTS;    VALIDATION;    VERIFICATION;    WATER MELC;   

DOI  :  10.2172/921148
RP-ID  :  SAND2007-6218
PID  :  OSTI ID: 921148
Others  :  TRN: US200803%%163

美国|英语

来源: SciTech Connect

【 摘 要 】

Before this LDRD research, no single tool could simulate a very high temperature reactor (VHTR) that is coupled to a secondary system and the sulfur iodine (SI) thermochemistry. Furthermore, the SI chemistry could only be modeled in steady state, typically via flow sheets. Additionally, the MELCOR nuclear reactor analysis code was suitable only for the modeling of light water reactors, not gas-cooled reactors. We extended MELCOR in order to address the above deficiencies. In particular, we developed three VHTR input models, added generalized, modular secondary system components, developed reactor point kinetics, included transient thermochemistry for the most important cycles [SI and the Westinghouse hybrid sulfur], and developed an interactive graphical user interface for full plant visualization. The new tool is called MELCOR-H2, and it allows users to maximize hydrogen and electrical production, as well as enhance overall plant safety. We conducted validation and verification studies on the key models, and showed that the MELCOR-H2 results typically compared to within less than 5% from experimental data, code-to-code comparisons, and/or analytical solutions.