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                             14 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accelerator driven systems (ADS) for energy production and waste transmutation: International trends in R&D Gokhale, Pratibha A.
2006
48 2 p. 91-102
12 p.
artikel
2 A four-group analytic rod transport problem for (n, γ) and (n, n′γ) verification Favorite, Jeffrey A.
2006
48 2 p. 103-134
32 p.
artikel
3 A simple model for the neutron slowing down calculations Jehouani, A.
2006
48 2 p. 173-180
8 p.
artikel
4 Continuous flow chemical processing on a microchip using microunit operations and a multiphase flow network [Progress in Nuclear Energy 47 (2005) 434–438] Tokeshi, Manabu
2006
48 2 p. 182-
1 p.
artikel
5 Core concept of compound process fuel cycle [Progress in Nuclear Energy 47 (2005) 231–238] Ikegami, Tetsuo
2006
48 2 p. 181-
1 p.
artikel
6 Current status of the feasibility study on commercialized fast reactor cycle systems and reactor core performance of the promising fast reactors [Progress in Nuclear Energy 47 (2005) 300–313] Kotake, Shoji
2006
48 2 p. 185-
1 p.
artikel
7 Development of a simple reprocessing process using selective precipitant for uranyl ions: Fundamental studies for evaluating the precipitant performance [Progress in Nuclear Energy 47 (2005) 406–413] Koshino, Nobuyoshi
2006
48 2 p. 186-
1 p.
artikel
8 Development of the innovative nuclide separation system for high-level radioactive waste using microchannel chip—extraction behavior of metal ions from aqueous phase to organic phase in microchannel [Progress in Nuclear Energy 47 (2005) 439–447] Hotokezaka, Hiroyasu
2006
48 2 p. 187-
1 p.
artikel
9 Development of the KAERI FEP, scenario, and assessment method database for permanent disposal of HLW in Korea Hwang, Y.S.
2006
48 2 p. 165-172
8 p.
artikel
10 Effect of different cross-section data sets on reflectors of a typical material test research reactor Ahmad, Siraj-ul-Islam
2006
48 2 p. 155-164
10 p.
artikel
11 Gas cooled fast reactor for generation IV service [Progress in Nuclear Energy 47 (2005) 271–282] Hejzlar, Pavel
2006
48 2 p. 184-
1 p.
artikel
12 Safety and neutronics: A comparison of MOX vs UO2 fuel Trellue, Holly R.
2006
48 2 p. 135-145
11 p.
artikel
13 The pumping performances of the turbomolecular pump simulated by Direct Simulation Monte Carlo method [Progress in Nuclear Energy 47 (2005) 664–671] Wang, Sheng
2006
48 2 p. 183-
1 p.
artikel
14 Validation of RELAP5/MOD3.2 model of VVER440 on reactor scram transient Groudev, Pavlin
2006
48 2 p. 146-154
9 p.
artikel
                             14 gevonden resultaten
 
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