nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A comprehensive review on clay swelling and illitization of smectite in natural subsurface formations and engineered barrier systems
|
Ohazuruike, Lotanna |
|
|
55 |
4 |
p. 1495-1506 |
artikel |
2 |
Acute oral toxicity and bioavailability of uranium and thorium in contaminated soil
|
Rashid, Nur Shahidah Abdul |
|
|
55 |
4 |
p. 1460-1467 |
artikel |
3 |
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations
|
Chen, Jiahao |
|
|
55 |
4 |
p. 1428-1438 |
artikel |
4 |
Approximate residual stress and plastic strain profiles for laser-peened alloy 600 surfaces
|
Park, Eui-Kyun |
|
|
55 |
4 |
p. 1250-1264 |
artikel |
5 |
Assessment of CUPID code used for condensation heat transfer analysis under steam-air mixture conditions
|
Hwang, Ji-Hwan |
|
|
55 |
4 |
p. 1400-1409 |
artikel |
6 |
Assessment of public knowledge, perception, and acceptance of nuclear power in Bangladesh
|
Hosan, Md Iqbal |
|
|
55 |
4 |
p. 1410-1419 |
artikel |
7 |
Beam position measurement system at HIRFL-CSRm
|
Li, Min |
|
|
55 |
4 |
p. 1332-1341 |
artikel |
8 |
BEPU analysis of a CANDU LBLOCA RD-14M experiment using RELAP/SCDAPSIM
|
Trivedi, A.K. |
|
|
55 |
4 |
p. 1448-1459 |
artikel |
9 |
Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT
|
Hu, Jiaqi |
|
|
55 |
4 |
p. 1280-1286 |
artikel |
10 |
Cavitation state identification of centrifugal pump based on CEEMD-DRSN
|
Dai, Cui |
|
|
55 |
4 |
p. 1507-1517 |
artikel |
11 |
Comparative study of CFD and 3D thermal-hydraulic system codes in predicting natural convection and thermal stratification phenomena in an experimental facility
|
Graževičius, Audrius |
|
|
55 |
4 |
p. 1555-1562 |
artikel |
12 |
Convergence study of traditional 2D/1D coupling method for k-eigenvalue neutron transport problems with Fourier analysis
|
Kong, Boran |
|
|
55 |
4 |
p. 1350-1364 |
artikel |
13 |
Correlation between the concentration of TeO2 and the radiation shielding properties in the TeO2–MoO3–V2O5 glass system
|
Al-Hadeethi, Y. |
|
|
55 |
4 |
p. 1218-1224 |
artikel |
14 |
Dynamic data validation and reconciliation for improving the detection of sodium leakage in a sodium-cooled fast reactor
|
Park, Sangjun |
|
|
55 |
4 |
p. 1528-1539 |
artikel |
15 |
Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks
|
Park, Ho Jin |
|
|
55 |
4 |
p. 1563-1570 |
artikel |
16 |
Experimental and numerical investigation on the pressure pulsation in reactor coolant pumps under different inflow conditions
|
Huang, Song |
|
|
55 |
4 |
p. 1310-1323 |
artikel |
17 |
Experimental consideration for contact angle and force acting on bubble under nucleate pool boiling
|
Park, Ji-Hwan |
|
|
55 |
4 |
p. 1269-1279 |
artikel |
18 |
Feasibility study of using triple-energy CT images for improving stopping power estimation
|
Kim, Yejin |
|
|
55 |
4 |
p. 1342-1349 |
artikel |
19 |
Geochemical and S isotopic studies of pollutant evolution in groundwater after acid in situ leaching in a uranium mine area in Xinjiang
|
Liu, Zhenzhong |
|
|
55 |
4 |
p. 1476-1484 |
artikel |
20 |
High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite
|
Lee, Jongyoul |
|
|
55 |
4 |
p. 1540-1554 |
artikel |
21 |
Impacts of halloysite clay nanoparticles on the structural and γ-ray shielding properties of the epoxy resin
|
Mahmoud, K.G. |
|
|
55 |
4 |
p. 1585-1590 |
artikel |
22 |
Impedance investigation of the surface film formed on aluminum alloy exposed to nuclear reactor emergency core coolant
|
Huang, Junlin |
|
|
55 |
4 |
p. 1518-1527 |
artikel |
23 |
Investigation of 180W separation by transient single withdrawal cascade using Salp Swarm optimization algorithm
|
Imani, Morteza |
|
|
55 |
4 |
p. 1225-1232 |
artikel |
24 |
Measurement of nuclear fuel assembly’s bow from visual inspection’s video record
|
Plašienka, Dušan |
|
|
55 |
4 |
p. 1485-1494 |
artikel |
25 |
Molecular dynamics study of ionic diffusion and the FLiNaK salt melt structure
|
Galashev, A.Y. |
|
|
55 |
4 |
p. 1324-1331 |
artikel |
26 |
Monitoring in a reinforced concrete structure for storing low and intermediate level radioactive waste. Lessons learnt after 25 years
|
Rebolledo, Nuria |
|
|
55 |
4 |
p. 1199-1209 |
artikel |
27 |
New Monte-Carlo based simulation program suitable for low-energy ions irradiation in pure materials
|
Al-Malkawi, Ghadeer H. |
|
|
55 |
4 |
p. 1287-1299 |
artikel |
28 |
Numerical study to reproduce a real cable tray fire event in a nuclear power plant
|
Lee, Jaiho |
|
|
55 |
4 |
p. 1571-1584 |
artikel |
29 |
Performance evaluation of plasma nitrided 316L stainless steel during long term high temperature sodium exposure
|
Singh, Akash |
|
|
55 |
4 |
p. 1468-1475 |
artikel |
30 |
Phase analysis of simulated nuclear fuel debris synthesized using UO2, Zr, and stainless steel and leaching behavior of the fission products and matrix elements
|
Tonna, Ryutaro |
|
|
55 |
4 |
p. 1300-1309 |
artikel |
31 |
Radiation dosimetry of 89Zr labeled antibody estimated using the MIRD method and MCNP code
|
Yazdi, Saeideh Izadi |
|
|
55 |
4 |
p. 1265-1268 |
artikel |
32 |
Sealing design optimization of nuclear pressure relief valves based on the polynomial chaos expansion surrogate model
|
Zong, Chaoyong |
|
|
55 |
4 |
p. 1382-1399 |
artikel |
33 |
Shielding analyses supporting the Lithium loop design and safety assessments in IFMIF-DONES
|
Stankunas, Gediminas |
|
|
55 |
4 |
p. 1210-1217 |
artikel |
34 |
Structural integrity assessment procedure of PCSG unit block using homogenization method
|
Youn, Gyogeun |
|
|
55 |
4 |
p. 1365-1381 |
artikel |
35 |
Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel
|
Irkimbekov, Ruslan А. |
|
|
55 |
4 |
p. 1439-1447 |
artikel |
36 |
Study on three-dimensional numerical simulation of shell and tube heat exchanger of the surface ship under marine conditions
|
Liao, Yi |
|
|
55 |
4 |
p. 1233-1243 |
artikel |
37 |
Techno-economic assessment of a very small modular reactor (vSMR): A case study for the LINE city in Saudi Arabia
|
Khan, Salah Ud-Din |
|
|
55 |
4 |
p. 1244-1249 |
artikel |
38 |
The effect of the number of subintervals upon the quantification of the seismic probabilistic safety assessment of a nuclear power plant
|
Kim, Ji Suk |
|
|
55 |
4 |
p. 1420-1427 |
artikel |