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                             44 results found
no title author magazine year volume issue page(s) type
1 Activation product interpretation of structural material for fast critical assemblies Keith, Corey
2018
119 C p. 98-105
article
2 A new and rigorous SPN theory – Part III: A succinct summary of the GSPN theory, the P3 equivalent GSP 3 ( 3 ) and implementation issues Chao, Yung-An
2018
119 C p. 310-321
article
3 Application of implicit Roe-type scheme and Jacobian-Free Newton-Krylov method to two-phase flow problems Hu, Guojun
2018
119 C p. 180-190
article
4 Applying conformal mapping method to Hybrid Nodal Green’s Function Method for two-dimensional simplified HTTR core calculation Lin, Tzung-Yi
2018
119 C p. 419-426
article
5 ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes Bandini, G.
2018
119 C p. 427-439
article
6 A theoretical model for the vibration of fuel rod with multi spans supported by springs Yan, B.H.
2018
119 C p. 257-263
article
7 Autonomous operation algorithm for safety systems of nuclear power plants by using long-short term memory and function-based hierarchical framework Lee, Daeil
2018
119 C p. 287-299
article
8 Bubble behavior and its contribution to heat transfer of subcooled flow boiling in a vertical rectangular channel Yuan, Dewen
2018
119 C p. 191-202
article
9 Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage Arkoma, Asko
2018
119 C p. 129-138
article
10 Comparative study on nuclear characteristics of APR1400 between 100% MOX core and UO2 core Salam, Mahrus
2018
119 C p. 374-381
article
11 Derivation of radiological source term of Korean Design System-Integrated Modular Advanced ReacTor (SMART) Mehboob, Khurram
2018
119 C p. 148-161
article
12 Determination of thorium fission rate based on 135I in thorium oxide cylinder bombarded by D-T fusion neutrons Zheng, Lei
2018
119 C p. 264-270
article
13 Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems Biondo, Elliott D.
2018
119 C p. 7-22
article
14 Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project Perez-Martin, S.
2018
119 C p. 454-473
article
15 DSS application on single-phase natural circulation in a simple rectangular loop Li, Xiangbin
2018
119 C p. 214-228
article
16 Editorial Board 2018
119 C p. ii
article
17 Effect of void propagation to sodium void reactivity in transient analyses of fast reactors with sodium-plenum Takeda, Toshikazu
2018
119 C p. 175-179
article
18 Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review Zhou, Wei
2018
119 C p. 66-86
article
19 Experimental study of supercritical water heat transfer deteriorations in different channels Li, Hong-bo
2018
119 C p. 240-256
article
20 Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor Matuzas, V.
2018
119 C p. 440-453
article
21 Extension of the reactor dynamics code DYN3D to SFR applications – Part III: Validation against the initial phase of the Phenix EOL natural convection test Nikitin, E.
2018
119 C p. 390-395
article
22 Extension of the reactor dynamics code DYN3D to SFR applications – Part II: Validation against the Phenix EOL control rod withdrawal tests Nikitin, E.
2018
119 C p. 411-418
article
23 Extension of the reactor dynamics code DYN3D to SFR applications – Part I: Thermal expansion models Nikitin, E.
2018
119 C p. 382-389
article
24 Fault detectability analysis in PCA method during condition monitoring of sensors in a nuclear power plant Li, Wei
2018
119 C p. 342-351
article
25 Fuel cycle and neutronic performance of a spectral shift molten salt reactor design Betzler, Benjamin R.
2018
119 C p. 396-410
article
26 Importance of parametric uncertainty in predicting probability distributions for burst wait-times in fissile systems Winter, George E.
2018
119 C p. 117-128
article
27 Influence of accident tolerant fuel cladding material on the European pressurised reactor core neutronic characteristics Boettcher, Agnieszka
2018
119 C p. 203-213
article
28 Investigation on reverse flow phenomena in UTSGs under two-phase natural circulation with low steam quality Chu, Xi
2018
119 C p. 1-6
article
29 Monte Carlo perturbation methods using “virtual density” theory for calculating reactivity due to geometry change Yamamoto, Toshihiro
2018
119 C p. 362-373
article
30 New developments in modeling sodium spray fires with ASTEC-Na Lebel, Luke S.
2018
119 C p. 23-35
article
31 New developments in sodium pool fire and SFR containment aerosol modeling with ASTEC-Na Lebel, Luke S.
2018
119 C p. 229-239
article
32 [No title] Williams, M.M.R.
2018
119 C p. 162
article
33 Numerical analysis of 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event using GOTHIC Yildiz, Mustafa Alper
2018
119 C p. 46-65
article
34 Numerical study on hydrodynamic and thermal characteristics of spent fuel pool Yu, Cheng-Lun
2018
119 C p. 139-147
article
35 Optimization of CABRI power transients with the SPARTE code and the URANIE uncertainty platform Clamens, O.
2018
119 C p. 271-278
article
36 Overview of filtered containment venting system in Nuclear Power Plants in Asia Yang, Jun
2018
119 C p. 87-97
article
37 Probability distribution for neutron density of two energy group point kinetics system Aboanber, Ahmed E.
2018
119 C p. 300-309
article
38 Reactor core power mapping based on Bayesian inference Peng, Xingjie
2018
119 C p. 322-330
article
39 Reducing the plutonium stockpile around the world using a new design of VVER-1200 assembly Galahom, A. Abdelghafar
2018
119 C p. 279-286
article
40 Risk analysis of high level radioactive waste storage tank based on HAZOP Zou, Shuliang
2018
119 C p. 106-116
article
41 Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors Fichot, F.
2018
119 C p. 36-45
article
42 Study on thermal fragmentation characteristics of a superheated alumina droplet Zambaux, J.A.
2018
119 C p. 352-361
article
43 The digital simulation and fuzzy evaluation to reduce the likelihood of unsafe behavior in nuclear decommissioning Li, Meng-kun
2018
119 C p. 331-341
article
44 Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process Chen, Yen-Shu
2018
119 C p. 163-174
article
                             44 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands