Digital Library
Close Browse articles from a journal
     Journal description
       All volumes of the corresponding journal
         All issues of the corresponding volume
                                       All articles of the corresponding issues
 
                             50 results found
no title author magazine year volume issue page(s) type
1 Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review Abdellatif, Hossam H.

168 C p.
article
2 A hybrid Analytical Discrete Ordinates-Response Matrix Constant Nodal method for one-speed X, Y-geometry transport problems Moraes, Leonardo R.C.

168 C p.
article
3 Analysis method for aerosol deposition behavior under sodium spray fire Yu, Zhitong

168 C p.
article
4 Analysis of loss of flow without scram test in the FFTF reactor – Part I: Preparation of neutronics data Nikitin, Evgeny

168 C p.
article
5 Analysis of nuclear microreactor efficacy with hydrogen production methods Kalinichenko, Dimitri

168 C p.
article
6 An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Fault diagnosis Mendoza, Mario

168 C p.
article
7 An inter-channel mixing model based on the void distribution in a rod bundle He, Ming-yue

168 C p.
article
8 Cementation of degraded residues of spent radioactive organic solvents by fenton oxidation Chen, Lei

168 C p.
article
9 CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system Humayun, Muhammad Shummas

168 C p.
article
10 Cohesive, elastic and anisotropic properties of s-, p- and d-block fission metals substituted Fe–Zr intermetallics Ali, Kawsar

168 C p.
article
11 Control strategies and performance analysis for a novel nuclear heating system with heat storage Liu, Weiqi

168 C p.
article
12 Corrosion products deposition and its effects on conjugate heat transfer for helical cruciform fuel assembly Cong, Tenglong

168 C p.
article
13 Critical heat flux for downward flows in vertical round pipes Hirose, Yoshiyasu

168 C p.
article
14 Development of a flow intrusion model for effectiveness evaluation in nuclear power plant security system YAN, Zhenyu

168 C p.
article
15 Editorial Board
168 C p.
article
16 Effect of irradiation on thermal stability of nitric acid solutions of acetohydroxamic acid Obedkov, A.S.

168 C p.
article
17 Effect of metallic redox ions on the corrosion behavior of GTAW weldment of type 304L stainless steel in simulated non-radioactive PUREX and HLLW medium Shit, Gopinath

168 C p.
article
18 Encapsulation of radioactive stainless-steel corrosion products sludge in aluminum using hot isostatic pressing process and treatment suitability assessment Kang, Ki Joon

168 C p.
article
19 Equivalence method and transient flow characteristics of the integrated valve Yang, Linqing

168 C p.
article
20 Estimation of transuranic isotopes in irradiated fuel elements for pebble bed HTR on activity vector Zhang, Hongjian

168 C p.
article
21 Experimental demonstration of a data-driven control system for subcritical nuclear facility Yu, Jiankai

168 C p.
article
22 Experimental study of the depressurization phenomena of supercritical carbon dioxide system Liu, Minyun

168 C p.
article
23 Flow blockage accident analysis in a multi purposes research reactor using Relap5 system code Deghal Cheridi, Amina Lyria

168 C p.
article
24 Gamma-ray spectra of post-irradiated uranium salt for total mass accounting with sodium-22 tracer Van Zile, Matthew

168 C p.
article
25 Neutron fission chain behavior for modern 235U multiplicity data Durkee Jr., Joe W.

168 C p.
article
26 Nuclear safety operating margin using new power peaking factors for NUR nuclear research reactor Sidi-Ali, K.

168 C p.
article
27 Numerical simulation of thermal hydraulics of supercritical pressure water with 2×2 rod assembly wrapped differently with a wire Kumar, Gaurav

168 C p.
article
28 Numerical study on a 7-pin bundle fuel assembly with different wire arrangements Li, Yaodi

168 C p.
article
29 Numerical study on flow structure and heat transfer of supercritical CO2 in tubes with different inclination angles Hou, Junren

168 C p.
article
30 Numerical study on thermal hydraulics characteristics during steam submerged jet condensation from rectangular CD nozzle Quddus, Abdul

168 C p.
article
31 Physical optimization and safety analysis of space thermionic reactor Xie, Lin

168 C p.
article
32 Possibility of YH1.85 and MgO–BeO as a moderator in high temperature reactors Tiftikci, Ali

168 C p.
article
33 Prediction of sodium leakage droplet size distribution in sodium-cooled fast reactor loop Xu, Zhen

168 C p.
article
34 Preliminary analysis of startup transient for an ultra-small lithium-cooled space reactor power system Ge, Li

168 C p.
article
35 Preliminary analysis of the irradiation deformation of a typical molten salt reactor graphite component Wang, Yong

168 C p.
article
36 Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver Guilbaud, Thomas

168 C p.
article
37 Radiation safety assessments for radioactive concrete recycling workers and residents Kim, Min Ji

168 C p.
article
38 Radiological characterization plan for decommissioning IFIN-HH's Cyclotron Ionescu, E.

168 C p.
article
39 Reactor lightweight shielding optimization method based on parallel embedded genetic particle-swarm hybrid algorithm Zheng, Songchuan

168 C p.
article
40 Reactor reliability modeling and reliable life analysis method for multi-state space reactor systems based on DBN and interval estimation Chen, Ziwei

168 C p.
article
41 Release of windowed multipole library for ENDF/B-VIII.0 in support of OpenMC criticality and depletion analysis Yu, Jiankai

168 C p.
article
42 SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model Ko, Yujoeng

168 C p.
article
43 Shifting to a 36-month fuel cycle with advanced moderating burnable absorbers enabling high assay low enriched uranium (HALEU) Bolukbasi, M.J.

168 C p.
article
44 The application of trajectory analysis method and Fast Fourier Transform analysis method in the division of flow instability influence regions under ocean conditions Wang, Sipeng

168 C p.
article
45 The effect of the radial heat loss, upper reservoir temperature, and corrugated wall channel on the flooding critical heat flux Nahon, Lior

168 C p.
article
46 Thermal and radiation shielding characteristics of erbium ions doped zinc tellurite glasses Nazrin, S.N

168 C p.
article
47 Time-dependent simplified D P 1 approximation for neutron transport equation Nazari, M.

168 C p.
article
48 TRU utilization and MA transmutation in thorium-based fluorinated molten salt fast reactor Li, Dongguo

168 C p.
article
49 Using life cycle assessment to quantify the environmental benefits of circular economy strategies in the nuclear industry Pucciarelli, Martina

168 C p.
article
50 Xenon behavior modeling for molten salt reactors by using multiple transport mechanisms Wu, Chen

168 C p.
article
                             50 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands