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                             53 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accident tolerant fuel thermal hydraulic behaviors evaluation during loss of coolant accident in CPR1000 Yu, Honghao

139 C p.
artikel
2 A fuzzy-PID composite controller for core power control of liquid molten salt reactor Zeng, Wenjie

139 C p.
artikel
3 A methodology for digital mockup update based on the 3D scanned spatial information for the automated dismantling of nuclear facilities Kim, Ikjune

139 C p.
artikel
4 Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS Taniguchi, Yoshinori

139 C p.
artikel
5 An experimental study of two-phase flow instability in a multi-loop natural circulation system Abbati, Zahraddeen

139 C p.
artikel
6 Anomalous reactivity swing in the 238U-233U system Wallenius, Janne

139 C p.
artikel
7 Application of Cuckoo Search algorithm to Loading Pattern Optimization problems Meneses, Anderson Alvarenga de Moura

139 C p.
artikel
8 A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors García, Manuel

139 C p.
artikel
9 Assembly pin factor parameterization method based on the proper orthogonal decomposition Li, Zhuo

139 C p.
artikel
10 A subgroup method based on the equivalent Dancoff-factor cell technique in APOLLO3® for thermal reactor calculations Mao, Li

139 C p.
artikel
11 A two-step neutron spectrum unfolding method for fission reactors based on artificial neural network Cao, Chenglong

139 C p.
artikel
12 Basic design parameter optimization on water cooled thorium breeder reactor Permana, Sidik

139 C p.
artikel
13 Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo Alhassan, E.

139 C p.
artikel
14 Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design Lee, Sung Nam

139 C p.
artikel
15 Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator Bae, Jin Whan

139 C p.
artikel
16 Design and analysis of improved two-phase natural circulation systems with thermoelectric generator Wang, Dongqing

139 C p.
artikel
17 Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications Zhang, Xuebei

139 C p.
artikel
18 Editorial Board
139 C p.
artikel
19 Effect of diamond additive on the fission gas release in UO2 fuel irradiated to 7.2 GWd/tHM Medvedev, Pavel

139 C p.
artikel
20 ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants Herranz, Luís Enrique

139 C p.
artikel
21 Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System) Bae, Byoung-Uhn

139 C p.
artikel
22 Experimental study on eutectic reaction between fuel debris and reactor structure using simulant materials Xiong, Zhihong

139 C p.
artikel
23 Experimental study on the vibration behavior of the pebble bed in PB-FHR Chen, Xingwei

139 C p.
artikel
24 Fitting-based resonance database method for resonance self-shielding calculations of large-scale task considering depletion and intra-pin distribution Qin, Shuai

139 C p.
artikel
25 Global sensitivity analysis of LOFT large break loss of coolant accident with optimized moment-independent method Xiong, Qingwen

139 C p.
artikel
26 Impact of grain size on performance degradation of TREAT LEU Schunert, Sebastian

139 C p.
artikel
27 Implementation and performance study of lpCMFD acceleration method for multi-energy group k-eigenvalue neutron transport problem in hexagonal geometry Chan, Yimeng

139 C p.
artikel
28 Investigation of LBLOCA in VVER-1000 NPP using RELAP5/SCDAP and CONTAIN codes Salehi, Mohsen

139 C p.
artikel
29 Linear optimization for predicting material compositions in molten salt reactors Wooten, Daniel

139 C p.
artikel
30 Management of loss of offsite power avoiding reactor trip Kim, Sungkyum

139 C p.
artikel
31 MCS – A Monte Carlo particle transport code for large-scale power reactor analysis Lee, Hyunsuk

139 C p.
artikel
32 MCS/TH1D analysis of VERA whole-core multi-cycle depletion problems Nguyen, Tung Dong Cao

139 C p.
artikel
33 Measurement and analysis of neutron leakage spectrum in depleted Uranium-Polyethylene Mock-up Lu, Xinxin

139 C p.
artikel
34 MLEM reconstruction method applied to partial defect verification using simulated data Shiba, Shigeki

139 C p.
artikel
35 Modeling uncertainty of instrument and control system of nuclear power plant Kaur, Raj kamal

139 C p.
artikel
36 New delayed neutron group constants and covariances for LWR core applications, combining summation calculations and integral experiments Leconte, P.

139 C p.
artikel
37 Non-intrusive detection of gas–water interface in circular pipes inclined at various angles Jo, Hongrae

139 C p.
artikel
38 Optimal time step length and statistics in Monte Carlo burnup simulations Dufek, Jan

139 C p.
artikel
39 Pre-CHF boiling heat transfer performance on tube bundles with or without enhanced surfaces - a review Ren, Shuai

139 C p.
artikel
40 Prediction of unmeasurable parameters of NPPs using different model-free methods based on cross-correlation detection of measurable/unmeasurable parameters: A comparative study Moshkbar-Bakhshayesh, Khalil

139 C p.
artikel
41 Recent measurements on plutonium-thorium fuel by substitution experiments in the ZED-2 critical facility Adams, F.P.

139 C p.
artikel
42 Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor Pilehvar, A.F.

139 C p.
artikel
43 Study of the PWR ex-core detector response simulation based on the 3D S N method Xu, Longfei

139 C p.
artikel
44 Study on strip-shaped liquid film in the corrugated plate dryer Wang, Bo

139 C p.
artikel
45 The effect of base irradiation on failure behaviors of UO2 and chromia-alumina additive fuels under simulated reactivity-initiated accidents: A comparative analysis with FEMAXI-8 Udagawa, Yutaka

139 C p.
artikel
46 The safety improvement of VVER-1000 NPP against SBO accident using portable air-cooled diesel generator Jabbari, M.

139 C p.
artikel
47 The unified model for irradiation embrittlement prediction of reactor pressure vessel Li, Chengliang

139 C p.
artikel
48 Three-dimensional thermal hydraulic transient calculation of coupled cold and hot sodium pools under a loss of feedwater accident in the China experimental fast reactor Xia, Zihan

139 C p.
artikel
49 Toward the implementation of self-powered, wireless, real-time reactor power sensing Turso, James

139 C p.
artikel
50 Uncertainty quantification of fuel pebble model and its effect on the uncertainty propagation of nuclear data in pebble bed HTR Cheng, Youying

139 C p.
artikel
51 Validation of actinide nuclear data based on reactivity worth experiments in a MOX-LWR spectrum Leconte, P.

139 C p.
artikel
52 Water hammer analysis when switching of parallel pumps based on contra-motion check valve Yang, Zhida

139 C p.
artikel
53 Whole-core depletion calculation using domain decomposed continuous-energy Monte Carlo simulation via McBOX with p-CMFD acceleration and inline feedback Jo, YuGwon

139 C p.
artikel
                             53 gevonden resultaten
 
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