| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Acceleration of the outer iterations of the space-dependent neutron kinetics equations solution
|
Zimin, Vyacheslav G.
|
|
1996
|
|
17 |
p. 1407-1424
18 p.
|
artikel
|
| 2 |
A comparative study to investigate burnup in research reactor fuel using two independent experimental methods
|
Iqbal, Masood
|
|
2001
|
|
17 |
p. 1733-1744
12 p.
|
artikel
|
| 3 |
A co-ordinate transformation technique for studying flux perturbations induced by strong vibrating absorbers
|
Sahni, D.C.
|
|
1999
|
|
17 |
p. 1551-1567
17 p.
|
artikel
|
| 4 |
A methodology for optimisation of countermeasures for animal products after a nuclear accident and its application
|
Hwang, Won Tae
|
|
1999
|
|
17 |
p. 1537-1550
14 p.
|
artikel
|
| 5 |
An application of the ‘end-point’ method to the minimum critical mass problem in two group transport theory
|
Williams, M.M.R.
|
|
2003
|
|
17 |
p. 1707-1729
23 p.
|
artikel
|
| 6 |
ANEMONA: multiassembly neutron transport modeling
|
Jevremovic, Tatjana
|
|
2002
|
|
17 |
p. 2105-2125
21 p.
|
artikel
|
| 7 |
An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies
|
Chun, Moon-Hyun
|
|
2001
|
|
17 |
p. 1683-1695
13 p.
|
artikel
|
| 8 |
Angular exposure build up factors for combined energy photons emitted from a line geometry radioactive source
|
Eduardo, Bojorquez
|
|
1999
|
|
17 |
p. 1593-1599
7 p.
|
artikel
|
| 9 |
An integrated framework for effective reduction of occupational radiation exposure in a nuclear power plant
|
Hyun Moon, Joo
|
|
1998
|
|
17 |
p. 1429-1440
12 p.
|
artikel
|
| 10 |
A nodal collocation method for the calculation of the lambda modes of the P L equations
|
Capilla, M.
|
|
2005
|
|
17 |
p. 1825-1853
29 p.
|
artikel
|
| 11 |
Application of boron and gadolinium burnable poison particles in UO2 and PUO2 fuels in HTRs
|
Kloosterman, J.L.
|
|
2003
|
|
17 |
p. 1807-1819
13 p.
|
artikel
|
| 12 |
Application of the HGPT methodology of reactor operation problems with a nodal mixed method
|
Baudron, A.M.
|
|
1998
|
|
17 |
p. 1383-1402
20 p.
|
artikel
|
| 13 |
Application of the P N method to the matrix form transport equation
|
Caldeira, Alexandre D.
|
|
2005
|
|
17 |
p. 1889-1894
6 p.
|
artikel
|
| 14 |
Artificial neural networks for dynamic monitoring of simulated-operating parameters of high temperature gas cooled engineering test reactor (HTTR)
|
Şeker, Serhat
|
|
2003
|
|
17 |
p. 1777-1791
15 p.
|
artikel
|
| 15 |
A simple analytical method for evaluation of limit-cycle oscillation amplitude in boiling water reactors
|
Hashimoto, Kengo
|
|
1998
|
|
17 |
p. 1455-1464
10 p.
|
artikel
|
| 16 |
A solution of the neutron diffusion equation for a hemisphere with mixed boundary conditions
|
Cassell, J.S.
|
|
2004
|
|
17 |
p. 1987-2004
18 p.
|
artikel
|
| 17 |
A two-component equilibrium-diffusion limit
|
Morel, Jim E.
|
|
2004
|
|
17 |
p. 2049-2057
9 p.
|
artikel
|
| 18 |
A variational principle in probabilistic dynamics
|
Labeau, P.E.
|
|
2000
|
|
17 |
p. 1543-1575
33 p.
|
artikel
|
| 19 |
Burnup waves
|
Van Dam, Hugo
|
|
1998
|
|
17 |
p. 1409-1417
9 p.
|
artikel
|
| 20 |
Calculational tools to conduct experimental optimization in Tehran research reactor
|
Khalafi, H
|
|
1999
|
|
17 |
p. 1601-1610
10 p.
|
artikel
|
| 21 |
Calculation of radiation attenuation coefficients for shielding concretes
|
Bashter, I.I.
|
|
1997
|
|
17 |
p. 1389-1401
13 p.
|
artikel
|
| 22 |
Calculation of the moderator temperature coefficient of reactivity for water moderated reactors
|
Mourtzanos, K
|
|
2001
|
|
17 |
p. 1773-1782
10 p.
|
artikel
|
| 23 |
Characteristics of hydriding and hydrogen embrittlement of the Ti–Al–Zr alloy
|
Kim, Tae-Kyu
|
|
2002
|
|
17 |
p. 2041-2053
13 p.
|
artikel
|
| 24 |
CHF prediction in nuclear fuel elements by using round tube data
|
Auxiliadora Fortini, Maria
|
|
2002
|
|
17 |
p. 2071-2085
15 p.
|
artikel
|
| 25 |
Coupled scalar and vector PN methods for solving multigroup transport problems in multislab geometry
|
Dias, A.F.
|
|
2000
|
|
17 |
p. 1607-1626
20 p.
|
artikel
|
| 26 |
Cross-section measurements for the (n,p) and (n,α) reactions on 23Na and for the (n,p) reaction on 26Mg at the neutron energies from 13.6 to 14.9 MeV
|
Bostan, M
|
|
2002
|
|
17 |
p. 2019-2027
9 p.
|
artikel
|
| 27 |
Current papers in nuclear energy
|
|
|
1996
|
|
17 |
p. 1425-1428
4 p.
|
artikel
|
| 28 |
Development of a back propagation network for one-step transient DNBR calculations
|
Kim, Hee-Cheol
|
|
1997
|
|
17 |
p. 1437-1446
10 p.
|
artikel
|
| 29 |
Development of BWR regional instability model and verification based on ringhals 1 test
|
Hotta, Akitoshi
|
|
1997
|
|
17 |
p. 1403-1427
25 p.
|
artikel
|
| 30 |
Development of severe accident management advisory and training simulator (SAMAT)
|
Jeong, Kwang-Sub
|
|
2002
|
|
17 |
p. 2055-2069
15 p.
|
artikel
|
| 31 |
DYN1D-MSR dynamics code for molten salt reactors
|
Krepel, Jiri
|
|
2005
|
|
17 |
p. 1799-1824
26 p.
|
artikel
|
| 32 |
Editorial to: Edward Larsen’s 60th birthday
|
Adams, Marvin L.
|
|
2004
|
|
17 |
p. 1959-1960
2 p.
|
artikel
|
| 33 |
Ed Larsen: Applied mathematician, English Major, enthusiastic accelerator
|
|
|
2004
|
|
17 |
p. 1961-
1 p.
|
artikel
|
| 34 |
Estimation of the 237Np(n,2n) [237Np(γ,n) + 237Np(n,2n)] reaction rate ratio in the mixed n-γ fields associated with the thermal neutron induced fission of 235U and the spontaneous fission of 252Cf
|
Croft, S.
|
|
1997
|
|
17 |
p. 1429-1435
7 p.
|
artikel
|
| 35 |
Fast-neutrons incident on holmium
|
Smith, Alan B.
|
|
2001
|
|
17 |
p. 1745-1758
14 p.
|
artikel
|
| 36 |
FN approximation of the solution to a singular integral equation of classical reactor physics
|
Ganapol, B.D.
|
|
2004
|
|
17 |
p. 2017-2024
8 p.
|
artikel
|
| 37 |
Heuristic derivation of rossi-alpha formula with delayed neutrons and correlated source
|
Yamane, Yoshihiro
|
|
1998
|
|
17 |
p. 1373-1382
10 p.
|
artikel
|
| 38 |
Hugo van Dam and the dynamic adjoint function
|
Pázsit, Imre
|
|
2003
|
|
17 |
p. 1757-1775
19 p.
|
artikel
|
| 39 |
“I have an idea!” An appreciation of Edward W. Larsen’s contributions to particle transport
|
Adams, Marvin L.
|
|
2004
|
|
17 |
p. 1963-1986
24 p.
|
artikel
|
| 40 |
Influence of the external neutron sources in the criticality prediction using 1/M curve
|
Pereira, Valmir
|
|
2005
|
|
17 |
p. 1875-1888
14 p.
|
artikel
|
| 41 |
In honour of Professor Hugo van Dam on the occasion of his retirement
|
van der Hagen, Tim
|
|
2003
|
|
17 |
p. 1703-1705
3 p.
|
artikel
|
| 42 |
Iterative computation of time-eigenvalues of the neutron transport equation
|
Lathouwers, D.
|
|
2003
|
|
17 |
p. 1793-1806
14 p.
|
artikel
|
| 43 |
Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation
|
Jatuff, F.
|
|
2003
|
|
17 |
p. 1731-1755
25 p.
|
artikel
|
| 44 |
Much ado about nothing: response matrices for void regions
|
Lewis, E.E.
|
|
2004
|
|
17 |
p. 2025-2037
13 p.
|
artikel
|
| 45 |
New results on the neutron-induced fission cross-section of 231Pa for incident neutron energies E n =0.8–3.5MeV
|
Oberstedt, S.
|
|
2005
|
|
17 |
p. 1867-1874
8 p.
|
artikel
|
| 46 |
Nuclear Reactor Physics
|
Williams, M.M.R.
|
|
2001
|
|
17 |
p. 1783-1787
5 p.
|
artikel
|
| 47 |
Obituary: Memories of Ivan Kuščer 1918–2000
|
|
|
2000
|
|
17 |
p. 1535-1542
8 p.
|
artikel
|
| 48 |
On the internal interface perturbation
|
Rahnema, F.
|
|
1996
|
|
17 |
p. 1401-1406
6 p.
|
artikel
|
| 49 |
On the master equation approach to transport in discrete random media in the presence of scattering
|
Prinja, Anil K.
|
|
2004
|
|
17 |
p. 2005-2016
12 p.
|
artikel
|
| 50 |
On the spectral analysis of iterative solutions of the discretized one-group transport equation
|
Sanchez, Richard
|
|
2004
|
|
17 |
p. 2059-2075
17 p.
|
artikel
|
| 51 |
On the WIMKAL-88 library
|
Caldeira, A.D.
|
|
1997
|
|
17 |
p. 1461-1462
2 p.
|
artikel
|
| 52 |
Optimization of MOX enrichment distributions in typical LWR assemblies using a simplex method-based algorithm
|
Cuevas Vivas, G.F.
|
|
2002
|
|
17 |
p. 2001-2017
17 p.
|
artikel
|
| 53 |
Pinhole collimator design for nuclear survey system
|
Lee, Wanno
|
|
2002
|
|
17 |
p. 2029-2040
12 p.
|
artikel
|
| 54 |
Point kinetic model for fluid fuel systems
|
Lapenta, G.
|
|
2001
|
|
17 |
p. 1759-1772
14 p.
|
artikel
|
| 55 |
Prediction of two-phase mixture density using artificial neural networks
|
Lombardi, C.
|
|
1997
|
|
17 |
p. 1373-1387
15 p.
|
artikel
|
| 56 |
Predictions of some spontaneous fission decay modes
|
Ronen, Yigal
|
|
1997
|
|
17 |
p. 1457-1459
3 p.
|
artikel
|
| 57 |
Probabilistic dynamics: Estimation of generalized unreliability through efficient Monte Carlo simulation
|
Labeau, P.E.
|
|
1996
|
|
17 |
p. 1355-1369
15 p.
|
artikel
|
| 58 |
PWR system simulation and parameter estimation with neural networks
|
Akkurt, Hatice
|
|
2002
|
|
17 |
p. 2087-2103
17 p.
|
artikel
|
| 59 |
Safety analysis of a supercritical pressure, light water cooled and moderated reactor with double tube water rods
|
Okano, Yasushi
|
|
1997
|
|
17 |
p. 1447-1456
10 p.
|
artikel
|
| 60 |
Safety characteristics of the multipurpose fast reactor (MPFR)
|
Netchaev, Alexandre
|
|
2001
|
|
17 |
p. 1717-1732
16 p.
|
artikel
|
| 61 |
Sensitivity of reactivity insertion limits with respect to safety parameters in a typical MTR
|
Nasir, Rubina
|
|
1999
|
|
17 |
p. 1517-1535
19 p.
|
artikel
|
| 62 |
Statistical failure analysis of metallic U-10zr/HT9 fast reactor fuel pin by considering the weibull distribution and cumulative damage fraction
|
Nam, Cheol
|
|
1998
|
|
17 |
p. 1441-1453
13 p.
|
artikel
|
| 63 |
Statistical methods used for code-to-code comparisons in the OECD/NRC PWR MSLB benchmark
|
Taylor, J.Bryce
|
|
2000
|
|
17 |
p. 1589-1605
17 p.
|
artikel
|
| 64 |
Status of experimental and theoretical (n,4n) reaction cross-section data
|
Atasoy, Hamit
|
|
1998
|
|
17 |
p. 1403-1407
5 p.
|
artikel
|
| 65 |
Stochastic geometry capability in MCNP5 for the analysis of particle fuel
|
Brown, Forrest B.
|
|
2004
|
|
17 |
p. 2039-2047
9 p.
|
artikel
|
| 66 |
Synthesis of conservative discontinuous solutions for diffusion theory
|
Ackroyd, R.T.
|
|
1996
|
|
17 |
p. 1381-1399
19 p.
|
artikel
|
| 67 |
System unavailability calculations in biased Monte Carlo simulation: a possible pitfall
|
Marseguerra, Marzio
|
|
2000
|
|
17 |
p. 1577-1588
12 p.
|
artikel
|
| 68 |
The effect of stochastic perturbation of fuel distribution on the criticality of a one speed reactor and the development of multi-material multinomial line statistics
|
Jahshan, S.N.
|
|
2001
|
|
17 |
p. 1697-1716
20 p.
|
artikel
|
| 69 |
The interim fuel storage facility of the PBMR
|
Fuls, W.F.
|
|
2005
|
|
17 |
p. 1854-1866
13 p.
|
artikel
|
| 70 |
Thermal-hydraulic phenomena during reflux condensation cooling in steam generator tubes
|
Yong Jeong, Hae
|
|
1998
|
|
17 |
p. 1419-1428
10 p.
|
artikel
|
| 71 |
The slab albedo problem using singular eigenfunctions and the third form of the transport equation
|
Kaşkaş, A.
|
|
1996
|
|
17 |
p. 1371-1379
9 p.
|
artikel
|
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