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                             19 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A critical review of methods and models for evaluating organizational factors in Human Reliability Analysis Alvarenga, M.A.B.
2014
75 C p. 25-41
17 p.
artikel
2 Alternative processes of comminution and colamination of uranium molybdenum alloys Pasqualini, Enrique E.
2014
75 C p. 92-104
13 p.
artikel
3 Analysis of common cause failure effect on system reliability in seismic PSA Yu, Yu
2014
75 C p. 158-167
10 p.
artikel
4 A review of nuclear batteries Prelas, Mark A.
2014
75 C p. 117-148
32 p.
artikel
5 Assessment of the CUPID code applicability to the thermal-hydraulic analysis of a CANDU moderator system Park, Sang Ki
2014
75 C p. 72-79
8 p.
artikel
6 Benchmarking of the HTR-10 reactor's kinetic parameters: Effective delayed neutron fraction Hosseini, S.A.
2014
75 C p. 80-91
12 p.
artikel
7 Conceptual core design of an innovative small PWR utilizing fully ceramic microencapsulated fuel Dai, Xiang
2014
75 C p. 63-71
9 p.
artikel
8 Editorial Board 2014
75 C p. IFC-
1 p.
artikel
9 Evaluation of post accident molten material relocation time to the core catcher in a fast breeder reactor Jasmin Sudha, A.
2014
75 C p. 149-157
9 p.
artikel
10 Events related to emergency diesel generators in the nuclear industry: Analysis of lessons learned from the operating experience Kančev, Duško
2014
75 C p. 192-197
6 p.
artikel
11 Feasibility studies on the separation of ruthenium from high level liquid waste by constant potential electro-oxidation Swain, Pravati
2014
75 C p. 198-206
9 p.
artikel
12 Film splitting model with entrainment Schulthess, J.L.
2014
75 C p. 180-191
12 p.
artikel
13 Investigations on single-phase natural circulation loop dynamics. Part 2: Role of wall constitutive laws Naveen, Kumar
2014
75 C p. 105-116
12 p.
artikel
14 LES analysis of the flow in a simplified PWR assembly with mixing grid Bieder, Ulrich
2014
75 C p. 15-24
10 p.
artikel
15 Material corrosion in a reactor containment sump following a loss-of-coolant accident Lahti, Erik
2014
75 C p. 1-9
9 p.
artikel
16 Neutronics analysis of a small PWR utilizing carbon coated fuel with diffusion theory code PRIDE Khan, Ammar
2014
75 C p. 10-14
5 p.
artikel
17 New strategies with multi-model, state-feedback control and stability analysis for load-follow PWR core Li, Gang
2014
75 C p. 168-179
12 p.
artikel
18 Roles and effects of pyroprocessing for spent nuclear fuel management in South Korea Ahn, Joonhong
2014
75 C p. 49-62
14 p.
artikel
19 Validation of a fuel management code MCODE-FM against fission product poisoning and flux wire measurements of the MIT reactor Sun, Kaichao
2014
75 C p. 42-48
7 p.
artikel
                             19 gevonden resultaten
 
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