Results 31 to 40 of about 2,762 (182)
Nuclear Engineering and Technology, 2021 This paper presents the verification and validation (V&V) of a calculation module for isotope inventory prediction to control the back-end cycle of spent nuclear fuel (SNF).
Jaerim Jang +5 more
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Jacobian-free Newton Krylov two-node coarse mesh finite difference based on nodal expansion method
Nuclear Engineering and Technology, 2022 A Jacobian-Free Newton Krylov Two-Nodal Coarse Mesh Finite Difference algorithm based on Nodal Expansion Method (NEM_TNCMFD_JFNK) is successfully developed and proposed to solve the three-dimensional (3D) and multi-group reactor physics models.
Xiafeng Zhou
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Validation of spent nuclear fuel decay heat calculation by a two-step method
Nuclear Engineering and Technology, 2021 In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs).
Jaerim Jang +5 more
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CORE DESIGN STUDY FOR A SMALL MODULAR BOILING WATER REACTOR [PDF]
EPJ Web of Conferences, 2021 The hybrid Small Modular Boiling Water Reactor (SMBWR) is a new conceptual design of BWR-type SMR. The main features of SMBWR include a natural circulation loop in its coolant recirculation system and external superheaters system integrated into the ...
Wibisono Andhika Feri, Shwageraus Eugene
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COUPLED TRANSIENT ANALYSIS OF A CORE WITH FUEL ASSEMBLY BOWING WITH A HYBRID CTF/DYN3D MODEL [PDF]
EPJ Web of Conferences, 2021 Fuel assembly bowing is a known phenomenon observed in many PWR reactors all over the world. The phenomenon is relevant to safety as it can lead to increased water gaps between assemblies which results in higher pin peaking factors.
Périn Y, Travleev A, Zilly M
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HIGH-PERFORMANCE MULTI-BATCH FUEL MANAGEMENTS FOR THE ADVANCED SOLUBLE-BORON-FREE ATOM CORE [PDF]
EPJ Web of Conferences, 2021 The autonomous transportable on-demand reactor module (ATOM), a 450 MWth PWR-type small modular reactor (SMR), is under development at Korea Advanced Institute of Science and Technology (KAIST).
Nguyen Xuan Ha +2 more
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Energies, 2021 The Korea Atomic Energy Research Institute (KAERI) has developed the DeCART2D 2-dimensional (2D) method of characteristics (MOC) transport code and the MASTER nodal diffusion code and has established its own two-step procedure. For design code licensing,
Ho Jin Park, Jin Young Cho
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Variational Nodal Method for Solving P1 Equation
Yuanzineng kexue jishuStarting from the neutron transport equation, the diffusion equation is firstly derived via the P1 approximation, and subsequently the neutron diffusion equation is obtained through the diffusion approximation.
LI Yisong, LI Yunzhao, FAN Yuwen, QIN Junwei, WANG Songzhe
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Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation
EPJ Web of Conferences, 2017 Safe operation of a nuclear reactor requires an extensive calculational support. Operational data are determined by full-core calculations during the design phase of a fuel loading.
Frybort Jan
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Energies, 2022 Targeting ultimate fidelity reactor physics calculations the Dynamic Monte Carlo (DMC) method simulates reactor transients without resorting to static or quasistatic approximations.
David Legrady +5 more
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