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                             41 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 An adaptive mesh refinement approach for average current nodal expansion method in 2-D rectangular geometry Poursalehi, N.
2013
55 C p. 61-70
10 p.
artikel
2 An incident flux expansion transport theory method suitable for coupling to diffusion theory methods in hexagonal geometry Hayward, Robert M.
2013
55 C p. 279-287
9 p.
artikel
3 APOLLO2 and TRIPOLI4 solutions of the OECD VVER-1000 LEU and MOX assembly benchmark Petrov, N.
2013
55 C p. 93-107
15 p.
artikel
4 A study on evaluation of pebble flow velocity with modification of the kinematic model for pebble bed reactor Kim, Song Hyun
2013
55 C p. 322-330
9 p.
artikel
5 Comparison of photon attenuation coefficients of various barite concretes and lead by MCNP code, XCOM and experimental data Shirmardi, S.P.
2013
55 C p. 288-291
4 p.
artikel
6 Comparison of thermal scattering processing options for S(α,β) cards in MCNP Čerba, Štefan
2013
55 C p. 18-22
5 p.
artikel
7 Concept of a high temperature integrated multi-modular thermal reactor Patel, Vishal
2013
55 C p. 312-321
10 p.
artikel
8 Confirmation of accuracy of generalized power series method for the solution of point kinetics equations with feedback Hamada, Yasser Mohamed
2013
55 C p. 184-193
10 p.
artikel
9 Development of a high order and multi-dimensional nodal code, ACNEC3D, for reactor core analysis Poursalehi, N.
2013
55 C p. 211-224
14 p.
artikel
10 Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor Hu, B.X.
2013
55 C p. 302-311
10 p.
artikel
11 Double differential cross sections of light charged particle emission of n + 27Al reaction Han, Yinlu
2013
55 C p. 75-92
18 p.
artikel
12 Editorial board 2013
55 C p. IFC-
1 p.
artikel
13 Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor mixed-core Lashkari, A.
2013
55 C p. 265-271
7 p.
artikel
14 Efficient estimation of the functional reliability of a passive system by means of an improved Line Sampling method Wang, Baosheng
2013
55 C p. 9-17
9 p.
artikel
15 Evaluation of core compositions for use in breed and burn reactors and limited-separations fuel cycles Petroski, Robert
2013
55 C p. 151-168
18 p.
artikel
16 Fractional-space law for the neutron current density Espinosa-Paredes, G.
2013
55 C p. 120-125
6 p.
artikel
17 Gas threshold pressure and gas permeability of silo concrete specimens for a low- and intermediate-level waste disposal facility in Korea Kim, Juyub
2013
55 C p. 1-8
8 p.
artikel
18 Goal based mesh adaptivity for fixed source radiation transport calculations Baker, C.M.J.
2013
55 C p. 169-183
15 p.
artikel
19 Investigation of shielding properties of some boron compounds İçelli, Orhan
2013
55 C p. 341-350
10 p.
artikel
20 Investigation on radiation shielding parameters of bismuth borosilicate glass from 1keV to 100GeV Chanthima, N.
2013
55 C p. 23-28
6 p.
artikel
21 Investigations of flow and temperature field development in bare and wire-wrapped reactor fuel pin bundles cooled by sodium Govindha Rasu, N.
2013
55 C p. 29-41
13 p.
artikel
22 Measurement of gamma attenuation for ANR end shield model using CaSO4:Dy phosphor Bakshi, A.K.
2013
55 C p. 205-210
6 p.
artikel
23 Modelling of VVER-440/213 hermetic rooms in training simulator Nagy, Attila
2013
55 C p. 272-278
7 p.
artikel
24 Monte Carlo analysis of the propagation of fusion neutrons in a high enriched uranium system Difilippo, Felix C.
2013
55 C p. 126-136
11 p.
artikel
25 Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes Rachamin, R.
2013
55 C p. 194-204
11 p.
artikel
26 Neutronic design of a very high temperature reactor core with low graphite content Telésforo-Reyes, Dionisio
2013
55 C p. 71-74
4 p.
artikel
27 Numerical investigation of thermal–hydraulic characteristics in a steam generator using a coupled primary and secondary side heat transfer model Li, Yanjun
2013
55 C p. 258-264
7 p.
artikel
28 Numerical simulations and laboratory experiments for evaluating the characteristics of pollutant transport Suh, Kyung-Suk
2013
55 C p. 55-60
6 p.
artikel
29 Optimising the energy group structure used for fusion systems Morgan, L.
2013
55 C p. 108-115
8 p.
artikel
30 Optimum burnup of BAEC TRIGA research reactor Lyric, Zoairia Idris
2013
55 C p. 225-229
5 p.
artikel
31 Performance of refractometry in quantitative estimation of isotopic concentration of heavy water in nuclear reactor Dhole, K.
2013
55 C p. 116-119
4 p.
artikel
32 Public exposure from environmental release of radioactive material under normal operation of unit-1 Bushehr nuclear power plant Sohrabi, M.
2013
55 C p. 351-358
8 p.
artikel
33 The effect of calm conditions and wind intervals in low wind speed on atmospheric dispersion factors Jeong, Hyojoon
2013
55 C p. 230-237
8 p.
artikel
34 The numerical solution of the point kinetics equation using the matrix exponential method Park, Yujin
2013
55 C p. 42-48
7 p.
artikel
35 Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code Kim, Hee-Kyung
2013
55 C p. 331-340
10 p.
artikel
36 Thermo-hydraulic characteristics of the helically coiled tube and the condensate heat exchanger for SMART Chung, Young-Jong
2013
55 C p. 49-54
6 p.
artikel
37 Three-dimensional Monte Carlo calculation of gas production in structural material of APEX reactor for some evaluated data files Günay, Mehtap
2013
55 C p. 292-296
5 p.
artikel
38 Time-of-flight discrimination between gamma-rays and neutrons by using artificial neural networks Akkoyun, S.
2013
55 C p. 297-301
5 p.
artikel
39 Transient analyses for lead–bismuth cooled accelerator-driven system Sugawara, Takanori
2013
55 C p. 238-247
10 p.
artikel
40 TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs Cuvelier, Marie-Hermine M.
2013
55 C p. 137-150
14 p.
artikel
41 Visual numerical steering in 3D AGENT code system for advanced nuclear reactor modeling and design Hernandez, Hermilo
2013
55 C p. 248-257
10 p.
artikel
                             41 gevonden resultaten
 
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