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                             48 results found
no title author magazine year volume issue page(s) type
1 Acceleration of fission source convergence in the Serpent 2 Monte Carlo code using a response matrix based solution for the initial source distribution Leppänen, Jaakko
2019
128 C p. 63-68
article
2 A deformed Doppler Broadening Function considering the Tsallis speed distribution Guedes, Guilherme
2019
128 C p. 414-421
article
3 A deterministic-stochastic energy-hybrid method for neutron-transport calculation Zheng, Qi
2019
128 C p. 292-299
article
4 Advanced passive residual heat removal system for high power pool-type research reactor Hwang, Won-Ki
2019
128 C p. 94-101
article
5 An adaptive variance reduction algorithm based on RMC code for solving deep penetration problems Pan, Qingquan
2019
128 C p. 171-180
article
6 A new inventory tracking method for Mark-V electrorefiner Yoo, Tae-Sic
2019
128 C p. 406-413
article
7 Application of melt-refining process to transition state of CANDLE burning fast reactor Osato, Hiroki
2019
128 C p. 77-83
article
8 Approach to optimization of risk assessment based on an evaluation matrix for decommissioning processes of a nuclear facility Jeong, KwanSeong
2019
128 C p. 53-62
article
9 Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory Abrate, Nicolò
2019
128 C p. 455-470
article
10 Assessment of SiC-CMC compatibility with components of actinide fuel systems Gerczak, Tyler J.
2019
128 C p. 127-139
article
11 Assessment of thermal neutron scattering in a heavy paraffinic molecular material Manring, Cole A.
2019
128 C p. 140-147
article
12 A stochastic differential equation for neutron count with detector dead time and applications to the Feynman-α formula Dubi, Chen
2019
128 C p. 380-389
article
13 Calculation of adjoint-weighted reactor kinetics parameters in OpenMC Peng, Xingjie
2019
128 C p. 231-235
article
14 Closed U-Pu and Th-U cycle in sixteen selected reactors: Comparison of major equilibrium features Krepel, J.
2019
128 C p. 341-357
article
15 Continuous-energy Monte Carlo neutron transport on GPUs in the Shift code Hamilton, Steven P.
2019
128 C p. 236-247
article
16 Delayed fission energy effect on LWR normal operation and transients Liu, Yuxuan
2019
128 C p. 84-93
article
17 Development of critical experiments to provide validation data for multiphysics coupling codes Dupont, Mathieu N.
2019
128 C p. 256-267
article
18 Development of MELCOR thermal hydraulic model of AP1000 and its verification for a DECL break Malicki, M.
2019
128 C p. 44-52
article
19 Editorial Board 2019
128 C p. ii
article
20 Experimental and numerical study on helium flow characteristics in randomly packed pebble bed Wu, Zhenxing
2019
128 C p. 268-277
article
21 Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations Ernoult, M.
2019
128 C p. 69-76
article
22 Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion Labouré, Vincent
2019
128 C p. 443-454
article
23 Investigation on the impact of thermal-kernel effect of lithium hydride on the reactivity of nuclear propulsion particle bed reactor Wang, Lipeng
2019
128 C p. 24-32
article
24 Measuring risk-importance in a Dynamic PRA framework Mandelli, D.
2019
128 C p. 160-170
article
25 Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor Rykhlevskii, Andrei
2019
128 C p. 366-379
article
26 Neutronic evaluation of the steady-state operation of a 20 kWth Aqueous Homogeneous Reactor for Mo-99 production Pérez, Daniel Milian
2019
128 C p. 148-159
article
27 Neutronic performance characteristics of different LEU fuels in a proposed NIST research reactor Turkoglu, Danyal J.
2019
128 C p. 209-215
article
28 Numerical investigation of an advanced U-RANS based pressure fluctuation model to simulate non-linear vibrations of nuclear fuel rods due to turbulent parallel-flow Kottapalli, S.
2019
128 C p. 115-126
article
29 Off-design performance and control characteristics of space reactor closed Brayton cycle system Li, Zhi
2019
128 C p. 318-329
article
30 Overtemperature protection systems for spallation target in China initiative accelerator driven sub-critical system Cui, Wenjuan
2019
128 C p. 358-365
article
31 Parametric study of iodine-129 releases from nuclear fuel to fuel-clad gap & primary coolant in PWRs Nasir, Rubina
2019
128 C p. 181-189
article
32 Performance of a passive cooling system for spent fuel pool using two-phase thermosiphon evaluated by RELAP5/MELCOR coupling analysis Huang, Zheng
2019
128 C p. 330-340
article
33 Physical characteristics of a PWR core loaded with micro-cell UO2 pellet fuels Hwang, Dae Hee
2019
128 C p. 33-43
article
34 PLIF experimental validation of a FLUENT CFD model of a coolant mixing in reactor vessel down-comer Eltayeb, Abdelgadir
2019
128 C p. 190-202
article
35 Reactivity monitoring of the accelerator driven VENUS-F subcritical reactor with the “current-to-flux” method Marie, N.
2019
128 C p. 12-23
article
36 Sensitivity analysis of the effect of spent fuel out-of-pile residence time and actinides recovery ratio on the performance of nuclear energy system with closed fuel cycle Hu, Y.
2019
128 C p. 278-287
article
37 Serpent/SCF pin-level multiphysics solutions for the VERA Fuel Assembly benchmark Ferraro, Diego
2019
128 C p. 102-114
article
38 SLOWPOKE-2 alternative core loading configurations analysis for highly improved reactor performance Puig, Francesc
2019
128 C p. 216-230
article
39 SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept Zhou, Shengcheng
2019
128 C p. 248-255
article
40 Standardized verification of the Cyclus fuel cycle simulator Bae, Jin Whan
2019
128 C p. 288-291
article
41 Temporal changes of geochemistry and microbial community in low and intermediate level waste (LILW) repository, South Korea Ahn, Jinmo
2019
128 C p. 309-317
article
42 The material-region-based 2D/1D transport method Liu, Zhouyu
2019
128 C p. 1-11
article
43 The numerical solution of space-dependent neutron kinetics equations in hexagonal-z geometry using backward differentiation formula with adaptive step size Cai, Yun
2019
128 C p. 203-208
article
44 Theoretical prediction of single bubble motion in vertically upward two-phase flow across inclined tube bundles Zhang, K.
2019
128 C p. 422-432
article
45 Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations Blaise, Patrick
2019
128 C p. 390-397
article
46 TREAT M2 experiment modeling for transient benchmark analysis Sorrell, Nina C.
2019
128 C p. 398-405
article
47 Uncertainty analysis on natural circulation characteristics under ocean conditions Wang, Chenyang
2019
128 C p. 300-308
article
48 Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core Qiao, Liang
2019
128 C p. 433-442
article
                             48 results found
 
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