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                             28 results found
no title author magazine year volume issue page(s) type
1 Actinide ENDF/B-VII cross-section evaluations and validation testing Chadwick, Mark B.
2009
36 3 p. 258-262
5 p.
article
2 A global approach to the physics validation of simulation codes for future nuclear systems Palmiotti, Giuseppe
2009
36 3 p. 355-361
7 p.
article
3 Analysis of the OECD/NEA ROSA Project experiment simulating a PWR small break LOCA with high-power natural circulation Takeda, Takeshi
2009
36 3 p. 386-392
7 p.
article
4 AP1000 core design with 50% MOX loading Fetterman, Robert J.
2009
36 3 p. 324-330
7 p.
article
5 A posteriori error estimator and AMR for discrete ordinates nodal transport methods Duo, Jose I.
2009
36 3 p. 268-273
6 p.
article
6 Application of TRACE/PARCS to BWR stability analysis Xu, Yunlin
2009
36 3 p. 317-323
7 p.
article
7 Burnable poison for reactivity management in a very high temperature reactor Jo, Chang Keun
2009
36 3 p. 298-304
7 p.
article
8 Core design studies for a 1000MWth Advanced Burner Reactor Kim, T.K.
2009
36 3 p. 331-336
6 p.
article
9 Delayed gamma studies from photo-fission of 237Np for nuclear waste characterization Dighe, P.M.
2009
36 3 p. 399-403
5 p.
article
10 Economy of uranium resources in a three-component reactor fleet with mixed thorium/uranium fuel cycles Wilson, J.N.
2009
36 3 p. 404-408
5 p.
article
11 Editorial Chawla, Rakesh
2009
36 3 p. 255-257
3 p.
article
12 Editorial board 2009
36 3 p. IFC-
1 p.
article
13 Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme Ferroukhi, H.
2009
36 3 p. 286-291
6 p.
article
14 Failure of high burnup fuels under reactivity-initiated accident conditions Sugiyama, Tomoyuki
2009
36 3 p. 380-385
6 p.
article
15 First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor Yamano, Hidemasa
2009
36 3 p. 337-343
7 p.
article
16 High resolution time integration for SN radiation transport Thoreson, Greg
2009
36 3 p. 263-267
5 p.
article
17 Improved Monte Carlo-perturbation method for estimation of control rod worths in a research reactor Kalcheva, Silva
2009
36 3 p. 344-349
6 p.
article
18 Improvement of the resonance scattering treatment in MCNP in view of HTR calculations Becker, B.
2009
36 3 p. 281-285
5 p.
article
19 Mixed-oxide (MOX) fuel performance benchmarks Ott, L.J.
2009
36 3 p. 375-379
5 p.
article
20 Modeling of LVRF critical experiments in ZED-2 using WIMS9A/PANTHER and MCNP5 Sissaoui, M.T.
2009
36 3 p. 292-297
6 p.
article
21 Monte Carlo study of photoneutron production in U-235 following perturbations in cross section data Clarke, S.D.
2009
36 3 p. 393-398
6 p.
article
22 Neutronic characterization of the MEGAPIE target Panebianco, Stefano
2009
36 3 p. 350-354
5 p.
article
23 Qualification of the APOLLO2.8 code package for the calculation of the fuel inventory and reactivity loss of UO x spent fuels in BWRs Leconte, Pierre
2009
36 3 p. 362-367
6 p.
article
24 Single-phase mixing studies by means of a directly coupled CFD/system-code tool Bertolotto, Davide
2009
36 3 p. 310-316
7 p.
article
25 Sustainability of electricity supply technology portfolio Roth, Stefan
2009
36 3 p. 409-416
8 p.
article
26 The impact of 238U resonance elastic scattering approximations on thermal reactor Doppler reactivity Lee, Deokjung
2009
36 3 p. 274-280
7 p.
article
27 TORT solutions to the NEA suite of benchmarks for 3D transport methods and codes over a range in parameter space Bekar, Kursat B.
2009
36 3 p. 368-374
7 p.
article
28 Towards validation of criticality calculations for systems with MOX powders Ivanova, Tatiana
2009
36 3 p. 305-309
5 p.
article
                             28 results found
 
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