nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A Compensator Design Controlling Neutron Flux Distribution via Observer Theory
|
Ho Park, Young |
|
1997 |
|
18 |
p. i- 1 p. |
artikel |
2 |
A fuzzy modeling approach to the identification of transients in nuclear components
|
Marseguerra, Marzio |
|
2004 |
|
18 |
p. 2093-2112 20 p. |
artikel |
3 |
A hexagonal percolation model for zone-dependent pore interlinkage fraction and its application to the prediction of fission gas release
|
Kim, Han-Chul |
|
1996 |
|
18 |
p. 1445-1457 13 p. |
artikel |
4 |
Algorithms — Optimal algorithm for collision probabilities calculation in 3-D rectangular-cylindrical geometries
|
Constantin, M. |
|
1997 |
|
18 |
p. 1477-1489 13 p. |
artikel |
5 |
Analysis of loss of flow accident at Pakistan research reactor-1
|
Bokhari, I.H. |
|
2005 |
|
18 |
p. 1963-1968 6 p. |
artikel |
6 |
Analysis of reactivity induced accidents at Pakistan Research Reactor-1
|
Bokhari, I.H |
|
2002 |
|
18 |
p. 2225-2234 10 p. |
artikel |
7 |
An experimental study on linear differential scattering coefficients of the radioactive compounds UO2(C2H3O2)2 ·2H2O and Th(NO3)4 ·5H2O at 60 keV
|
İçelli, Orhan |
|
2004 |
|
18 |
p. 2157-2168 12 p. |
artikel |
8 |
A practical method for calculation of mass-attenuation coefficients of β particles
|
Gürler, O. |
|
2005 |
|
18 |
p. 1918-1925 8 p. |
artikel |
9 |
Artificial neural networks for neutron source localization within sealed tanks
|
Antonopoulos-Domis, M. |
|
1996 |
|
18 |
p. 1477-1488 12 p. |
artikel |
10 |
A solution of the neutron diffusion equation for a hemisphere containing a uniform source
|
Williams, M.M.R. |
|
2004 |
|
18 |
p. 2169-2184 16 p. |
artikel |
11 |
Author index
|
|
|
1998 |
|
18 |
p. xvii-xviii nvt p. |
artikel |
12 |
Author index
|
|
|
1996 |
|
18 |
p. 1-2 2 p. |
artikel |
13 |
Author index (autogenerate for vol 31)
|
|
|
2004 |
|
18 |
p. XV-XVI nvt p. |
artikel |
14 |
Author Index Vol 28
|
|
|
2001 |
|
18 |
p. XIII-XIV nvt p. |
artikel |
15 |
Author index (vol 30 autogenerate)
|
|
|
2003 |
|
18 |
p. XIII-XIV nvt p. |
artikel |
16 |
A validation of copper, nickel and iron data in endf/b-vi.2, jef-2.2 and jendl-3.2 through a series of br-1 critical core analysis
|
Gil, Choong-Sup |
|
1998 |
|
18 |
p. 1565-1572 8 p. |
artikel |
17 |
Boiloff pattern transition during core uncovery in a small break loca
|
Lim, In Cheol |
|
1996 |
|
18 |
p. 1459-1476 18 p. |
artikel |
18 |
Burn-up characteristics of ADS system utilizing the fuel composition from MOX PWRs spent fuel
|
Marsodi, |
|
2002 |
|
18 |
p. 2173-2186 14 p. |
artikel |
19 |
CANDU-6 operation post-simulations using the reactor physics codes DRAGON/DONJON
|
Varin, E. |
|
2004 |
|
18 |
p. 2139-2155 17 p. |
artikel |
20 |
Concept and basic performance of an in-pile experimental reactor for fast breeder reactors using fast driver core
|
Obara, Toru |
|
1997 |
|
18 |
p. 1491-1513 23 p. |
artikel |
21 |
Cross-section measurements for the 97Mo (n,p) 97mNb reaction at the neutron energies from 13.6 to 14.9 MeV
|
Bostan, M. |
|
2003 |
|
18 |
p. 1821-1828 8 p. |
artikel |
22 |
Current papers in nuclear energy
|
|
|
1996 |
|
18 |
p. 1497-1499 3 p. |
artikel |
23 |
Dependence of exotic nuclides production on target and beam features
|
Ricciardi, M.V |
|
1999 |
|
18 |
p. 1643-1656 14 p. |
artikel |
24 |
Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1
|
Jeong, J.-J. |
|
1999 |
|
18 |
p. 1611-1642 32 p. |
artikel |
25 |
Development of conceptual design tool for liquid metal cooled-reactors
|
Gu Lee, Kwang |
|
1999 |
|
18 |
p. 1657-1668 12 p. |
artikel |
26 |
Discretizing the diffusion equation on unstructured polygonal meshes in two dimensions
|
Palmer, Todd S. |
|
2001 |
|
18 |
p. 1851-1880 30 p. |
artikel |
27 |
Erratum to: An application of the Wiener–Hopf method to the one-speed flat-flux problem in a half-space [Annals of Nuclear Energy 30 (2003) 1333–1345]
|
Cassell, J.S. |
|
2003 |
|
18 |
p. 1921- 1 p. |
artikel |
28 |
Evaluation of the integral quantities for incident fusion source neutrons in infinite medium
|
Şahn, Sümer |
|
1998 |
|
18 |
p. 1503-1519 17 p. |
artikel |
29 |
Extending the operable time of the Syrian MNSR
|
Albarhoum, M. |
|
2004 |
|
18 |
p. 2203-2209 7 p. |
artikel |
30 |
Fast-neutrons incident on rotors: Tantalum
|
Smith, Alan B. |
|
2005 |
|
18 |
p. 1926-1952 27 p. |
artikel |
31 |
First experience with a six-loop nodalization of a VVER-440 using a new coupled neutronic-thermohydraulics system KIKO3D-RETINA V1.1D
|
Farkas, István |
|
2002 |
|
18 |
p. 2235-2242 8 p. |
artikel |
32 |
F.R. Farmer O.B.E., F.R.S. 1914–2001
|
Ackroyd, R.T. |
|
2005 |
|
18 |
p. 1895-1897 3 p. |
artikel |
33 |
Gamma displacement cross-sections in various materials
|
Kwon, Junhyun |
|
2000 |
|
18 |
p. 1627-1642 16 p. |
artikel |
34 |
Groundwater contaminant transport in presence of colloids II: sensitivity and uncertainty analysis on literature case studies
|
Marseguerra, Marzio |
|
2001 |
|
18 |
p. 1799-1807 9 p. |
artikel |
35 |
Hanford Site Historic District: History of the Plutonium Production Facilities—1943–1990
|
Vande Putte, D. |
|
2003 |
|
18 |
p. 1919-1920 2 p. |
artikel |
36 |
H∞ Filtering for Dynamic Compensation of Self-Powered Neutron Detectors - A Linear Matrix Inequality Based Method -
|
Park, Moon-Ghu |
|
1999 |
|
18 |
p. 1669-1682 14 p. |
artikel |
37 |
Immobilization of 137Cs and 60Co in concrete matrix
|
Plecas, Ilija |
|
2003 |
|
18 |
p. 1899-1903 5 p. |
artikel |
38 |
Improved performances of the fast reactor calculational system ERANOS-ERALIB1 due to improved a priori nuclear data and consideration of additional specific integral data 1 1 Sponsored by BNFL.
|
Fort, E. |
|
2003 |
|
18 |
p. 1879-1898 20 p. |
artikel |
39 |
Index
|
|
|
2000 |
|
18 |
p. XV-XVI nvt p. |
artikel |
40 |
Inelastic neutron scattering and prompt fission neutron spectra for 237Np
|
Kornilov, N.V. |
|
2000 |
|
18 |
p. 1643-1667 25 p. |
artikel |
41 |
Information retrieval system for ENDF format libraries
|
Velloso-Ferreira, C. |
|
1997 |
|
18 |
p. 1515-1524 10 p. |
artikel |
42 |
Introducing the migration mode method for the solution of the space and energy dependent diffusion equation
|
Dall'Osso, Aldo |
|
2003 |
|
18 |
p. 1829-1845 17 p. |
artikel |
43 |
Investigations of the SAD design parameters for optimum experimental performance
|
Domańska, G. |
|
2004 |
|
18 |
p. 2127-2138 12 p. |
artikel |
44 |
Krylov sub-space methods for K-eigenvalue problem in 3-D neutron transport
|
Gupta, Anurag |
|
2004 |
|
18 |
p. 2113-2125 13 p. |
artikel |
45 |
List of contents
|
|
|
1998 |
|
18 |
p. v-xv nvt p. |
artikel |
46 |
List of contents
|
|
|
1996 |
|
18 |
p. iii-xiii nvt p. |
artikel |
47 |
Measurement of (n,α) cross-sections for short-lived products by 13.4–14.9 MEV neutrons
|
Kasugai, Yoshimi |
|
1998 |
|
18 |
p. 1485-1502 18 p. |
artikel |
48 |
Measurements of the (n, np+d) activation cross sections with 13.4–14.9 MeV neutrons using a fusion neutronics source/JAERI
|
Sakane, Hitoshi |
|
2003 |
|
18 |
p. 1847-1862 16 p. |
artikel |
49 |
Modeling the activity and scaling factor of 129I in the primary coolant and CVCS resin of operating PWR
|
Hwang, Ki Ha |
|
2005 |
|
18 |
p. 1898-1917 20 p. |
artikel |
50 |
Monte Carlo modeling of KAMINI
|
Mohapatra, D.K. |
|
2004 |
|
18 |
p. 2185-2194 10 p. |
artikel |
51 |
Multi-group theory of neutron noise induced by vibrating boundaries
|
Arzhanov, Vasiliy |
|
2002 |
|
18 |
p. 2143-2158 16 p. |
artikel |
52 |
Neutron cross-sections of 242Pu in the energy range 5–20 MeV
|
Tudora, Anabella |
|
2000 |
|
18 |
p. 1669-1681 13 p. |
artikel |
53 |
Neutron streaming in a cylindrical annulus: a review of theory and comparison of methods
|
Williams, M.M.R. |
|
2002 |
|
18 |
p. 2211-2224 14 p. |
artikel |
54 |
Numerical simulation of a free-falling liquid sodium droplet combustion
|
Okano, Yasushi |
|
2003 |
|
18 |
p. 1863-1878 16 p. |
artikel |
55 |
On the collision kernels for gas mixtures
|
Ivchenko, I.N. |
|
1996 |
|
18 |
p. 1489-1495 7 p. |
artikel |
56 |
On the use of silicon as thermal neutron filter
|
Adib, M. |
|
2003 |
|
18 |
p. 1905-1917 13 p. |
artikel |
57 |
On the use of the average chord length
|
Sanchez, Richard |
|
2004 |
|
18 |
p. 2211-2216 6 p. |
artikel |
58 |
Parameter estimation during a transient – application to BWR stability
|
Tambouratzis, T. |
|
2004 |
|
18 |
p. 2077-2092 16 p. |
artikel |
59 |
Parasitic neutron bragg reflections from large imperfect single crystals
|
Naguib, K. |
|
1998 |
|
18 |
p. 1553-1563 11 p. |
artikel |
60 |
PWS: an efficient code system for solving space-independent nuclear reactor dynamics
|
Aboanber, A.E |
|
2002 |
|
18 |
p. 2159-2172 14 p. |
artikel |
61 |
Reactivity worth measurement of the control blades of the University of Florida Training Reactor
|
Quintero-Leyva, Barbaro |
|
1997 |
|
18 |
p. 1463-1476 14 p. |
artikel |
62 |
Real and virtual sampling in variational processing of stochastic simulation in neutron transport: The one-dimensional rod
|
Allagi, Mabruk O. |
|
1998 |
|
18 |
p. 1521-1542 22 p. |
artikel |
63 |
Recent advances in the LTSN method for criticality calculations in slab geometry
|
Orengo, Gilberto |
|
2004 |
|
18 |
p. 2195-2202 8 p. |
artikel |
64 |
Simulation of loss-of-flow transients in research reactors
|
Housiadas, Christos |
|
2000 |
|
18 |
p. 1683-1693 11 p. |
artikel |
65 |
Simulation of reactivity transients in current MTRs
|
Mirza, Anwar M. |
|
1998 |
|
18 |
p. 1465-1484 20 p. |
artikel |
66 |
Study on kinetics of subcritical system
|
Iwanaga, K. |
|
2005 |
|
18 |
p. 1953-1962 10 p. |
artikel |
67 |
Study on multi-recycle transmutation of LLFP in light water reactor
|
Budi Setiawan, M |
|
2001 |
|
18 |
p. 1789-1797 9 p. |
artikel |
68 |
Systematics for (n,p) excitation functions in the neutron energy between 13.3 and 15.0 MeV
|
Kasugai, Yoshimi |
|
1996 |
|
18 |
p. 1429-1444 16 p. |
artikel |
69 |
Technical note: the integral form of the transport equation with a moving boundary
|
Cassell, J.S. |
|
2004 |
|
18 |
p. 2217-2219 3 p. |
artikel |
70 |
Temperature distribution in mixed ThO2–UO2 fuel rods located in blanket of an inertial fusion energy breeder
|
Yapıcı, Hüseyin |
|
2002 |
|
18 |
p. 2187-2209 23 p. |
artikel |
71 |
Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system
|
Yapıcı, Hüseyin |
|
2001 |
|
18 |
p. 1825-1850 26 p. |
artikel |
72 |
Temporal adaptive algorithm for TRAC-BF1/NEM/COBRA-TF coupled calculations in BWR safety analysis
|
Solı́s, Jorge |
|
2002 |
|
18 |
p. 2127-2141 15 p. |
artikel |
73 |
The Greuling–Goertzel and Wigner approximations in the theory of neutron slowing down
|
Larsen, Edward W. |
|
2001 |
|
18 |
p. 1809-1824 16 p. |
artikel |
74 |
Transport Theory Corrections to the Source-Sink Method for Reactor Lattice Calculations
|
Williams, M.M.R. |
|
2000 |
|
18 |
p. 1695-1715 21 p. |
artikel |
75 |
Validation of a computational model for the evaluation of fuel-coolant interaction under severe accidental condition in fast breeder reactors
|
Sawada, Tetsuo |
|
1998 |
|
18 |
p. 1543-1552 10 p. |
artikel |