| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accumulation and distribution of nutrients, radionuclides and metals by roots, stems and leaves of plants
|
Phuong, Huynh Truc
|
|
|
55 |
7 |
p. 2650-2655
|
artikel
|
| 2 |
Activity concentrations and radiological hazard assessments of 226Ra, 232Th, 40K, and 137Cs in soil samples obtained from the Dongnam Institute of Radiological & Medical Science, Korea
|
Lee, Jieun
|
|
|
55 |
7 |
p. 2388-2394
|
artikel
|
| 3 |
Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD
|
Jang, Sang Hoon
|
|
|
55 |
7 |
p. 2712-2722
|
artikel
|
| 4 |
A field determination method of D-T neutron source yields based on oxygen prompt gamma rays
|
Zhang, Xiongjie
|
|
|
55 |
7 |
p. 2572-2577
|
artikel
|
| 5 |
Analysis for the secondary gamma-ray emission for glasses irradiated with various doses of fast neutron: Case study borate and silicate glasses
|
Tashlykov, O.L.
|
|
|
55 |
7 |
p. 2366-2372
|
artikel
|
| 6 |
Applicability of abrasive waterjet cutting to irradiated graphite decommissioning
|
Perotti, Francesco
|
|
|
55 |
7 |
p. 2356-2365
|
artikel
|
| 7 |
A real-time unmeasured dynamic response prediction for nuclear facility pressure pipeline system
|
Oh, Seungin
|
|
|
55 |
7 |
p. 2642-2649
|
artikel
|
| 8 |
Assaying of SNM using Simultaneous Detection of Fission Neutrons and Gammas by Employing a Novel Phoswich Detector
|
Sonu,
|
|
|
55 |
7 |
p. 2662-2669
|
artikel
|
| 9 |
A study on the effect of material impurity concentration on radioactive waste levels for plans for decommissioning of nuclear power plant
|
Cha, Gilyong
|
|
|
55 |
7 |
p. 2489-2497
|
artikel
|
| 10 |
Design, setup and routine operation of a water treatment system for the monitoring of low activities of tritium in water
|
Azevedo, C.D.R.
|
|
|
55 |
7 |
p. 2349-2355
|
artikel
|
| 11 |
Development of hybrid resin to reduce silica in borated water
|
Akhtar, Ramzan
|
|
|
55 |
7 |
p. 2547-2555
|
artikel
|
| 12 |
Differential die-away technology applied to detect special nuclear materials
|
Zhang, Lianjun
|
|
|
55 |
7 |
p. 2483-2488
|
artikel
|
| 13 |
Effects of fission product doping on the structure, electronic structure, mechanical and thermodynamic properties of uranium monocarbide: A first-principles study
|
Liang, Ru-Ting
|
|
|
55 |
7 |
p. 2556-2566
|
artikel
|
| 14 |
Estimation of fuel operating ranges of fusion power plants
|
Entler, Slavomir
|
|
|
55 |
7 |
p. 2687-2696
|
artikel
|
| 15 |
Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity
|
Eom, Jeong-Hyeon
|
|
|
55 |
7 |
p. 2498-2503
|
artikel
|
| 16 |
Feasibility study of a resistive-type sodium aerosol detector with ZnO nanowires for sodium-cooled fast reactors
|
Lee, Jewhan
|
|
|
55 |
7 |
p. 2373-2379
|
artikel
|
| 17 |
Feasibility study on a stabilization method based on full spectrum reallocation for spectra having non-identical momentum features
|
Ko, Kilyoung
|
|
|
55 |
7 |
p. 2432-2437
|
artikel
|
| 18 |
Gamma ray attenuation behaviors and mechanism of boron rich slag/ epoxy resin shielding composites
|
Dong, Mengge
|
|
|
55 |
7 |
p. 2613-2620
|
artikel
|
| 19 |
Impact of PSI-KIT Nitriding model on hypothetical Spent Fuel Pool accident simulation
|
Malicki, Mateusz
|
|
|
55 |
7 |
p. 2504-2515
|
artikel
|
| 20 |
Improvement and validation of aerosol models for natural deposition mechanism in reactor containment
|
Li, Jishen
|
|
|
55 |
7 |
p. 2628-2641
|
artikel
|
| 21 |
Integral effect tests for intermediate and small break loss-of-coolant accidents with passive emergency core cooling system
|
Bae, Byoung-Uhn
|
|
|
55 |
7 |
p. 2438-2446
|
artikel
|
| 22 |
LEU+ loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme
|
Khalefih, Husam
|
|
|
55 |
7 |
p. 2578-2590
|
artikel
|
| 23 |
Low beta superconducting cavity system design for HIAF iLinac
|
Xu, Mengxin
|
|
|
55 |
7 |
p. 2466-2473
|
artikel
|
| 24 |
Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source part two: Study of H3BO3 and B-DTPA under neutron irradiation
|
Hutli, Ezddin
|
|
|
55 |
7 |
p. 2419-2431
|
artikel
|
| 25 |
Modeling of deposition and erosion of CRUD on fuel surfaces under sub-cooled nucleate boiling in PWR
|
Seo, Seungjin
|
|
|
55 |
7 |
p. 2591-2603
|
artikel
|
| 26 |
Modelling of the fire impact on CONSTOR RBMK-1500 cask thermal behavior in the open interim storage site
|
Poškas, Robertas
|
|
|
55 |
7 |
p. 2604-2612
|
artikel
|
| 27 |
Module level EMC verification method for replacement items in nuclear power plant
|
Lim, Hee-Taek
|
|
|
55 |
7 |
p. 2407-2418
|
artikel
|
| 28 |
Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis
|
Wu, Yiwei
|
|
|
55 |
7 |
p. 2474-2482
|
artikel
|
| 29 |
Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation
|
Bedenko, Sergey V.
|
|
|
55 |
7 |
p. 2678-2686
|
artikel
|
| 30 |
Numerical investigation on ballooning and rupture of a Zircaloy tube subjected to high internal pressure and film boiling conditions
|
Nguyen, Van Toan
|
|
|
55 |
7 |
p. 2454-2465
|
artikel
|
| 31 |
Off-design performance evaluation of multistage axial gas turbines for a closed Brayton cycle of sodium-cooled fast reactor
|
Choi, Jae Hyun
|
|
|
55 |
7 |
p. 2697-2711
|
artikel
|
| 32 |
Practical methods for GPU-based whole-core Monte Carlo depletion calculation
|
Kim, Kyung Min
|
|
|
55 |
7 |
p. 2516-2533
|
artikel
|
| 33 |
Radiometric examination of fertilizers and assessment of their health hazards, commonly used in Pakistan
|
Younis, Hannan
|
|
|
55 |
7 |
p. 2447-2453
|
artikel
|
| 34 |
Spatial resolution and natural image quality assessment evaluation of gamma camera image using pinhole collimator in lutetium-yttrium oxyorthosilicate scintillation detector
|
Kim, Kyuseok
|
|
|
55 |
7 |
p. 2567-2571
|
artikel
|
| 35 |
The development of training platform for CiADS using cave automatic virtual environment
|
Li, Jin-Yang
|
|
|
55 |
7 |
p. 2656-2661
|
artikel
|
| 36 |
The radiation shielding competence and imaging spectroscopic based studies of Iron ore region of Kozhikode district, Kerala
|
Arivazhagan, S.
|
|
|
55 |
7 |
p. 2380-2387
|
artikel
|
| 37 |
Thermal analysis and optimization of the new ICRH antenna Faraday Screen in EAST
|
Liang, Q.C.
|
|
|
55 |
7 |
p. 2621-2627
|
artikel
|
| 38 |
Thermal-hydraulic analysis of He–Xe gas mixture in 2×2 rod bundle wrapped with helical wires
|
Wang, Chenglong
|
|
|
55 |
7 |
p. 2534-2546
|
artikel
|
| 39 |
Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant
|
Nistor-Vlad, R.M.
|
|
|
55 |
7 |
p. 2670-2677
|
artikel
|
| 40 |
Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method
|
Chen, Lekang
|
|
|
55 |
7 |
p. 2395-2406
|
artikel
|
Tijdschrift beschrijving