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                             15 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor Suzuki, Tohru
2015
47 3 p. 240-252
13 p.
artikel
2 A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents Sofu, Tanju
2015
47 3 p. 227-239
13 p.
artikel
3 Comparison of neutronic behavior of UO2, (Th-233U)O2 and (Th-235U)O2 fuels in a typical heavy water reactor Mirvakili, Seyed Mohammad
2015
47 3 p. 315-322
8 p.
artikel
4 Computational fluid dynamics analysis of the Canadian deuterium uranium moderator tests at the Stern Laboratories Inc. Kim, Hyoung Tae
2015
47 3 p. 284-292
9 p.
artikel
5 Construction schedule delay risk assessment by using combined AHP-RII methodology for an international NPP project Hossen, Muhammed Mufazzal
2015
47 3 p. 362-379
18 p.
artikel
6 Design optimization of radiation shielding structure for lead slowing-down spectrometer system Kim, Jeong Dong
2015
47 3 p. 380-387
8 p.
artikel
7 Effects of ion irradiation on microstructure and properties of zirconium alloys—A review Yan, Chunguang
2015
47 3 p. 323-331
9 p.
artikel
8 Estimation of leak rate through circumferential cracks in pipes in nuclear power plants Park, Jai Hak
2015
47 3 p. 332-339
8 p.
artikel
9 Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND) Kim, Ho Sik
2015
47 3 p. 293-305
13 p.
artikel
10 Nuclear fuel cycle cost estimation and sensitivity analysis of unit costs on the basis of an equilibrium model Kim, S.K.
2015
47 3 p. 306-314
9 p.
artikel
11 Prolongation of the BOR-60 reactor operation Izhutov, Alexey l.
2015
47 3 p. 253-259
7 p.
artikel
12 Quantitative observation of co-current stratified two-phase flow in a horizontal rectangular channel Lee, Seungtae
2015
47 3 p. 267-283
17 p.
artikel
13 Safety aspects of intermediate heat transport and decay heat removal systems of sodium-cooled fast reactors Chetal, Subhash Chander
2015
47 3 p. 260-266
7 p.
artikel
14 Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads Kim, Ji-Su
2015
47 3 p. 340-350
11 p.
artikel
15 Structural assessment of reactor pressure vessel under multi-layered corium formation conditions Kim, Tae Hyun
2015
47 3 p. 351-361
11 p.
artikel
                             15 gevonden resultaten
 
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