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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