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Cross section generation for a conceptual horizontal, compact high temperature gas reactor
Kang Junsu,Seker Volkan,Ward Andrew,Jabaay Daniel,Kochunas Brendan,Downar Thomas 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.3
A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR methods have limitations for accurate simulation of the HC-HTGR using a neutron diffusion core neutronics simulator. Several super-cell model configurations were investigated to consider the spectral effect of neighboring cells. A new history variable was introduced for the existing library format to more accurately account for the history effect from neighboring nodes and reactivity control drums. The macroscopic cross section library was validated through comparison with cross sections generated using full core Monte Carlo models and single cell cross section for both 3D core steady-state problems and 2D and 3D depletion problems. Core calculations were then performed with the AGREE HTR neutronics and thermal-fluid core simulator using super-cell cross sections. With the new history variable, the super-cell cross sections were in good agreement with the full core cross sections even for problems with significant spectrum change during fuel shuffling and depletion.
( Cihan Comba ),( Sakir Volkan Erdogan ),( Aliye Erdogan ),( Aysenur Bagdatli ),( Busra Seker Atas ),( Omer Demir ),( Isa Aykut Ozdemir ) 대한산부인과학회 2021 Obstetrics & Gynecology Science Vol.64 No.6
Objective The authors present a surgical film for vulvar cancer surgery, which was performed via video endoscopy. Methods An 88-yearold woman with squamous cell carcinoma of the vulva and who underwent radical vulvectomy was treated with sentinel lymph node (SLN) and bilateral inguinofemoral lymphadenectomy, which is preferably performed via video endoscopic surgery with a near-infrared fluorescence video endoscopy system. SLN mapping was performed using indocyanine green and near-infrared fluorescence mapping. Results SLNs were detected in the left superficial inguinal area. The surgeons performed bilateral inguinofemoral lymphadenectomy. Conclusion No postoperative early or late complications developed, and the patient was discharged 7 days after surgery. Stage 1B vulvar cancer was identified.
Validation of Numerical Methods to Calculate Bypass Flow in a Prismatic Gas-Cooled Reactor Core
탁남일,김민환,임홍식,노재만,Timothy J. Drzewiecki,Volkan Seker,Thomas J. Downar,JOSEPH KELLY 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.6
For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of Michigan (U of M). One of the important requirements for GAMMA+ and AGREE is an accurate modeling capability of a bypass flow in a prismatic core. Recently, a series of air experiments were performed at Seoul National University (SNU) in order to understand bypass flow behavior and generate an experimental database for the validation of computer codes. The main objective of the present work is to validate the GAMMA+ and AGREE codes using the experimental data published by SNU. The numerical results of the two codes were compared with the measured data. A good agreement was found between the calculations and the measurement. It was concluded that GAMMA+ and AGREE can reliably simulate the bypass flow behavior in a prismatic core.
VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE
Tak, Nam-Il,Kim, Min-Hwan,Lim, Hong-Sik,Noh, Jae Man,Drzewiecki, Timothy J.,Seker, Volkan,Downar, Thomas J.,Kelly, Joseph Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.6
For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of Michigan (U of M). One of the important requirements for GAMMA+ and AGREE is an accurate modeling capability of a bypass flow in a prismatic core. Recently, a series of air experiments were performed at Seoul National University (SNU) in order to understand bypass flow behavior and generate an experimental database for the validation of computer codes. The main objective of the present work is to validate the GAMMA+ and AGREE codes using the experimental data published by SNU. The numerical results of the two codes were compared with the measured data. A good agreement was found between the calculations and the measurement. It was concluded that GAMMA+ and AGREE can reliably simulate the bypass flow behavior in a prismatic core.