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                             33 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A gelation facility for the preparation of ceramic microspheres Maji, D.

162 C p.
artikel
2 Analysis of UO2, UN and U–10Zr fuels burning in a MegaPower reactor with solid monolithic and independent fuel element core designs Ma, Kunfeng

162 C p.
artikel
3 A rapid approach to generate multi-unit event trees based on tree combinatorial calculation Peng, Pengcheng

162 C p.
artikel
4 A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification Gorton, Jacob P.

162 C p.
artikel
5 Cyber hardening of Nuclear Power Plants with real-time nuclear reactor operation, 1. Preliminary operational testing Root, Sam J.

162 C p.
artikel
6 Descriptor sliding mode observer based fault tolerant control for nuclear power plant with actuator and sensor faults Surjagade, Piyush V.

162 C p.
artikel
7 Development of schemes from a single cascade to multi-cascades for separation of regenerated uranium Zeng, Shi

162 C p.
artikel
8 Editorial Board
162 C p.
artikel
9 Effect of climate and component performance on optimized recuperated air Brayton cycles for nuclear microreactor power conversion McKellar, M.G.

162 C p.
artikel
10 Evaluation of Bentonite, attapulgite, and kaolinite as eco-friendly adsorbents in the treatment of real radioactive wastewater containing Cs-137 Muslim, Wasan A.

162 C p.
artikel
11 Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident Hidayati, Anni Nuril

162 C p.
artikel
12 Fluence calculations for the TRISO- particle fuel ION implantation experiment Krajewska, Zuzanna M.

162 C p.
artikel
13 Impact of iron corrosion on swell pressure of compacted barmer bentonite induced with thermal history Kale, Rohini C.

162 C p.
artikel
14 Inverse estimation scheme of radioactive source distributions inside building rooms based on monitoring air dose rates using LASSO: Theory and demonstration Shi, Wei

162 C p.
artikel
15 Investigation of specially designed bentonite samples as potential bricks with better radiation shielding properties El-Samrah, Moamen G.

162 C p.
artikel
16 Investigation of the pulsed neutron source method measuring the fission decay properties of a subcritical assembly with low-Z reflectors Gao, Yi

162 C p.
artikel
17 Investigations on boiling heat transfer characteristics in non-uniform heating U-Tube bundles under rolling motion Li, Zongkun

162 C p.
artikel
18 Large leakage sodium-water reaction accident analysis in a sodium-cooled fast reactor with paralleling steam generators Bai, Xi

162 C p.
artikel
19 Li2B4O7–Bi2O3–ZrO4–CaWO4 glass system for neutron protection in neutron applications Aygün, B.

162 C p.
artikel
20 Loss Of Flow Accident (LOFA) with protection in NUR nuclear research reactor; three dimensional analysis of a Fast LOFA and a Slow LOFA Akhal, N.

162 C p.
artikel
21 Method for control drum position critical search with Monte Carlo codes Price, Dean

162 C p.
artikel
22 Method study on failure probability and uncertainty analysis of stress corrosion cracking in fixed parts of PWR Kong, Deyan

162 C p.
artikel
23 Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface Wang, Zetao

162 C p.
artikel
24 Radiometric techniques for the detection and assessment of tritium in aqueous media - a review Parker, Andrew J.

162 C p.
artikel
25 Revisit interior penalty based diffusion synthetic acceleration for the SN transport equation discretized with discontinuous Galerkin method Zhou, Shengcheng

162 C p.
artikel
26 Steady-state analysis of ROSTOV-2 benchmark problem using SERPENT-2 and PARCS codes Kheradmand Saadi, M.

162 C p.
artikel
27 The acceleration of improved Tone's method in advanced reactor lattice neutron spectrum calculation Du, Xianan

162 C p.
artikel
28 The effects of cladding thermo-physical and thermo-chemical properties on the coping time during a PWR unmitigated LB-LOCA Alaleeli, Maithah

162 C p.
artikel
29 Thermodynamic analysis of nuclear closed cycle MHD space power system Liu, Fei-biao

162 C p.
artikel
30 The role of nuclear energy in the carbon neutrality goal Liu, Limin

162 C p.
artikel
31 Transient three-dimensional numerical simulation on asymmetrical flow and thermal characteristics of CEFR sodium pool under one secondary pump shaft stuck accident Zhang, Yuhao

162 C p.
artikel
32 Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC Cong, Tenglong

162 C p.
artikel
33 Variation of heat load due to in-vessel debris bed in IVR condition Park, Joon-Soo

162 C p.
artikel
                             33 gevonden resultaten
 
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