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                             31 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A method to determine the gamma-ray linear attenuation coefficient Celiktas, C.
2011
38 9 p. 2096-2100
5 p.
artikel
2 Analysis of a multigroup stylized CANDU half-core benchmark Pounders, Justin M.
2011
38 9 p. 2024-2078
55 p.
artikel
3 An analytical multigroup benchmark for (n, γ) and (n, n′, γ) verification of diffusion theory algorithms Ganapol, B.D.
2011
38 9 p. 2017-2023
7 p.
artikel
4 A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP Kim, Hong-Chul
2011
38 9 p. 1877-1883
7 p.
artikel
5 A review of CCFL phenomenon Al Issa, S.
2011
38 9 p. 1795-1819
25 p.
artikel
6 Best Linear Unbiased Estimation of the nuclear masses Bouriquet, Bertrand
2011
38 9 p. 1863-1866
4 p.
artikel
7 Calculation and evaluations for n+63,65,nat.Cu reactions Han, Yinlu
2011
38 9 p. 1852-1862
11 p.
artikel
8 CFD analysis of flow and heat transfer of turbulent pulsating flow in a tube in rolling motion Yan, B.H.
2011
38 9 p. 1833-1841
9 p.
artikel
9 Cross section recondensation method via generalized energy condensation theory Douglass, Steven
2011
38 9 p. 2105-2110
6 p.
artikel
10 Design studies of a typical PWR core using advanced computational tools and techniques Huda, M.Q.
2011
38 9 p. 1939-1949
11 p.
artikel
11 Determination of the critical crack length for steam generator tubing based on fracture-mechanics-based method Hu, Jun
2011
38 9 p. 1900-1905
6 p.
artikel
12 Development and validation of a heuristic model for evaluation of the team performance of operators in nuclear power plants Kim, Sa Kil
2011
38 9 p. 2005-2016
12 p.
artikel
13 Double differential cross sections of n+ 63,65,nat.Cu reactions Han, Yinlu
2011
38 9 p. 1950-1963
14 p.
artikel
14 Dynamical nuclear safeguard investigations in nuclear materials using Analytic Pair Values Woo, Tae-Ho
2011
38 9 p. 1916-1923
8 p.
artikel
15 Editorial board 2011
38 9 p. IFC-
1 p.
artikel
16 Effects of various spacer grid modeling on the neutronic parameters of the VVER-1000 reactor Pazirandeh, Ali
2011
38 9 p. 1978-1986
9 p.
artikel
17 Guidelines to determine the optimal variables for the MTC measurement by noise analysis Monteyne, Griet
2011
38 9 p. 1924-1929
6 p.
artikel
18 Higher order methods for burnup calculations with Bateman solutions Isotalo, A.E.
2011
38 9 p. 1987-1995
9 p.
artikel
19 Interaction of natural convection flow in multiple open cavities formed due to horizontal fins Sharma, Anil Kumar
2011
38 9 p. 1906-1915
10 p.
artikel
20 Iterative method for obtaining the prompt and delayed alpha-modes of the diffusion equation Singh, K.P.
2011
38 9 p. 1996-2004
9 p.
artikel
21 Methodology for developing channel disassembly criteria under severe accident conditions for PHWRs Singh, Ritu J.
2011
38 9 p. 1884-1890
7 p.
artikel
22 Optimization studies of fuel loading pattern for a typical Pressurized Water Reactor (PWR) using particle swarm method Yadav, R.D.S.
2011
38 9 p. 2086-2095
10 p.
artikel
23 REA analysis of the Iranian VVER-1000 core by modification of PRORIA code for annular pellets Altaha, S. Mahmoud
2011
38 9 p. 1930-1938
9 p.
artikel
24 Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark Pittarello, R.
2011
38 9 p. 1842-1851
10 p.
artikel
25 Simultaneous Model Selection, Robust Data Reconciliation and Outlier Detection with Swarm Intelligence in a Thermal Reactor Power calculation Valdetaro, Eduardo Damianik
2011
38 9 p. 1820-1832
13 p.
artikel
26 Some evaluations of basic nodal-like schemes for a selection of classical problems in particle transport theory Barichello, L.B.
2011
38 9 p. 2101-2104
4 p.
artikel
27 Spatially adaptive eigenvalue estimation for the S N equations on unstructured triangular meshes Lathouwers, D.
2011
38 9 p. 1867-1876
10 p.
artikel
28 Study of the bias of the MTC estimate by noise analysis due to the presence of feedback Monteyne, Griet
2011
38 9 p. 1964-1967
4 p.
artikel
29 The determination of the total mass attenuation coefficients and the effective atomic numbers for concentrated colemanite and Emet colemanite clay İçelli, Orhan
2011
38 9 p. 2079-2085
7 p.
artikel
30 The effect of a CANDU fuel bundle geometry variation on thermalhydraulic performance Bae, Jun Ho
2011
38 9 p. 1891-1899
9 p.
artikel
31 Void reactivity feedback in BWRs with MA bearing MOX fuels Jitka, Zakova
2011
38 9 p. 1968-1977
10 p.
artikel
                             31 gevonden resultaten
 
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