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                             35 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comparison of dose rate calculations for a spent fuel storage cask by using MCNP and SAS4 Chen, A.Y.
2008
35 12 p. 2296-2305
10 p.
artikel
2 Analysis of BDBA in RBMK-1500 reactor with long-term loss of heat removal from the core Kaliatka, A.
2008
35 12 p. 2219-2233
15 p.
artikel
3 An analytical solution for the general perturbative diffusion equation by integral transform techniques de Vilhena, M.T.M.B.
2008
35 12 p. 2410-2413
4 p.
artikel
4 A nuclear data oriented interface code for processing applications Noguere, G.
2008
35 12 p. 2259-2269
11 p.
artikel
5 A point kernel model for the energy deposited on samples from gamma radiation in a research reactor core Varvayanni, M.
2008
35 12 p. 2351-2356
6 p.
artikel
6 Calculation of the power peaking factor in a nuclear reactor using support vector regression models Bae, In Ho
2008
35 12 p. 2200-2205
6 p.
artikel
7 Cellular neural networks (CNN) simulation for the TN approximation of the time dependent neutron transport equation in slab geometry Hadad, Kamal
2008
35 12 p. 2313-2320
8 p.
artikel
8 Development and characterization of the control assembly system for the large 2400MWth Generation IV gas-cooled fast reactor Girardin, G.
2008
35 12 p. 2206-2218
13 p.
artikel
9 Development and validation of a cross-section interface for PARCS Stålek, Mathias
2008
35 12 p. 2397-2409
13 p.
artikel
10 Development of a method of evaluating an inventory of fission products for a pebble bed reactor Jeong, Hyedong
2008
35 12 p. 2161-2171
11 p.
artikel
11 Editorial board 2008
35 12 p. IFC-
1 p.
artikel
12 Effect of finite sample dimensions and total scatter acceptance angle on the gamma ray buildup factor Singh, Sukhpal
2008
35 12 p. 2414-2416
3 p.
artikel
13 Emergency management for a nuclear power plant using fuzzy cognitive maps Espinosa-Paredes, G.
2008
35 12 p. 2387-2396
10 p.
artikel
14 Equilibrium and pre-equilibrium calculations of neutron production in medium–heavy targets irradiated by protons up to 100MeV Aydın, Emine Gamze
2008
35 12 p. 2306-2312
7 p.
artikel
15 Establishment of risk-based accident scenarios using the master logic diagram related to LILW management in the temporary storage facility Ahn, Min Ho
2008
35 12 p. 2420-2425
6 p.
artikel
16 Estimation of station blackout frequency for Indian fast breeder test reactor Ramakrishnan, M.
2008
35 12 p. 2332-2337
6 p.
artikel
17 Experimental study on the natural circulation of a passive residual heat removal system for an integral reactor following a safety related event Park, Hyun-Sik
2008
35 12 p. 2249-2258
10 p.
artikel
18 IGSHIELD: A new interactive point kernel gamma ray shielding code Subbaiah, K.V.
2008
35 12 p. 2234-2242
9 p.
artikel
19 Maximization of representativity factors for experimental planning of cross-section measurements: An information theoretic approach Kumar, P.T.Krishna
2008
35 12 p. 2243-2248
6 p.
artikel
20 Maximum polar angle subtended by a right circular cylinder Favorite, Jeffrey A.
2008
35 12 p. 2195-2199
5 p.
artikel
21 Measurements of the total molecular differential attenuation coefficients of some compounds for scattering of γ-rays İçelli, Orhan
2008
35 12 p. 2327-2331
5 p.
artikel
22 Monte Carlo simulation of neutron transport in intense neutron fields Matthes, W.K.
2008
35 12 p. 2436-2439
4 p.
artikel
23 Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system Tian, Wenxi
2008
35 12 p. 2280-2287
8 p.
artikel
24 Numerical simulation of a potential CO2 ingress accident in a SFR employing an advanced energy conversion system Eoh, Jae-Hyuk
2008
35 12 p. 2172-2185
14 p.
artikel
25 One speed criticality problems for a bare slab and sphere: Some benchmark results – II Naz, S.
2008
35 12 p. 2426-2431
6 p.
artikel
26 On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations Vasiliev, Alexander
2008
35 12 p. 2432-2435
4 p.
artikel
27 Pulsed neutron source measurements in the subcritical ADS experiment YALINA-Booster Persson, Carl-Magnus
2008
35 12 p. 2357-2364
8 p.
artikel
28 Quantifying uncertainties in the estimation of safety parameters by using bootstrapped artificial neural networks Secchi, Piercesare
2008
35 12 p. 2338-2350
13 p.
artikel
29 Reliability assessment of passive containment isolation system using APSRA methodology Nayak, A.K.
2008
35 12 p. 2270-2279
10 p.
artikel
30 Rossi-α and Feynmann Y functions for non-Poissonian pulsed sources of neutrons in the stochastic pulsing method: Application to subcriticality monitoring in ADS and comparison with the results of Poissonian pulsed neutron sources Munoz-Cobo, J.L.
2008
35 12 p. 2375-2386
12 p.
artikel
31 Sensitivity analysis for delayed neutron data van Rooijen, W.F.G.
2008
35 12 p. 2186-2194
9 p.
artikel
32 The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis Lozano, Juan-Andrés
2008
35 12 p. 2365-2374
10 p.
artikel
33 The behavior of reactor power and flux resulting from changes in core-coolant temperature for a miniature neutron source reactor Ahmed, Y.A.
2008
35 12 p. 2417-2419
3 p.
artikel
34 The survival probability of neutrons in supercritical convex bodies using a time-dependent collision probability method Williams, M.M.R.
2008
35 12 p. 2288-2295
8 p.
artikel
35 Two-phase modeling of a gas phase fluidized bed reactor for the fluorination of uranium tetrafluoride Khani, M.H.
2008
35 12 p. 2321-2326
6 p.
artikel
                             35 gevonden resultaten
 
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