| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparative study of integral parameters for TRX and BAPL benchmark lattices of thermal reactors using the cross-section library generated from JENDL and JEF evaluated data files
|
Islam, S.M.T.
|
|
2009
|
51 |
2 |
p. 378-381
4 p.
|
artikel
|
| 2 |
A “Generation III+” nuclear reactor for space needs
|
Cammi, A.
|
|
2009
|
51 |
2 |
p. 347-354
8 p.
|
artikel
|
| 3 |
A novel concept of QUADRISO particles – Part III: Applications to the plutonium–thorium fuel cycle
|
Talamo, Alberto
|
|
2009
|
51 |
2 |
p. 274-280
7 p.
|
artikel
|
| 4 |
A parallel algorithm with interface prediction and correction for spherical geometric transport equation
|
Hong, Zhenying
|
|
2009
|
51 |
2 |
p. 268-273
6 p.
|
artikel
|
| 5 |
A review of corrosion product transport and radiation field buildup in boiling water reactors
|
Lin, Chien C.
|
|
2009
|
51 |
2 |
p. 207-224
18 p.
|
artikel
|
| 6 |
A study on a scenario using the PID method
|
Lee, S.H.
|
|
2009
|
51 |
2 |
p. 253-257
5 p.
|
artikel
|
| 7 |
Calculation of maximum release rates in alternative design changes in the thickness of the buffer for the engineered barrier system (EBS) in deep repository by using Amber code
|
Malekifarsani, A.
|
|
2009
|
51 |
2 |
p. 355-360
6 p.
|
artikel
|
| 8 |
Comparative population dose risks from nuclear fuel cycle closure and renewal of the commercial nuclear energy alternative in the U.S.
|
Pennington, Charles W.
|
|
2009
|
51 |
2 |
p. 290-296
7 p.
|
artikel
|
| 9 |
Development of a φ20mm annular centrifugal contactor for the hot test of the total TRPO process
|
Duan, Wuhua
|
|
2009
|
51 |
2 |
p. 313-318
6 p.
|
artikel
|
| 10 |
Disposal concept for LILW in Korea: Characterization methodology and the disposal priority
|
Ahn, Min Ho
|
|
2009
|
51 |
2 |
p. 327-333
7 p.
|
artikel
|
| 11 |
Editorial Board
|
|
|
2009
|
51 |
2 |
p. IFC-
1 p.
|
artikel
|
| 12 |
Effects of high density dispersion fuel loading on the dynamics of a low enriched uranium fueled material test research reactor
|
Muhammad, Farhan
|
|
2009
|
51 |
2 |
p. 339-346
8 p.
|
artikel
|
| 13 |
Estimation of the activation of local reactor shielding concretes
|
Alhajali, S.
|
|
2009
|
51 |
2 |
p. 374-377
4 p.
|
artikel
|
| 14 |
Experimental study of onset of subcooled annular flow boiling
|
Ahmadi, R.
|
|
2009
|
51 |
2 |
p. 361-365
5 p.
|
artikel
|
| 15 |
Fire in the hole: A review of national spent nuclear fuel disposal policy
|
Rogers, Kenneth A.
|
|
2009
|
51 |
2 |
p. 281-289
9 p.
|
artikel
|
| 16 |
Four energy group neutron flux distributions in the Syrian Miniature Neutron Source Reactor using the WIMSD4 and CITATION codes
|
Khattab, K.
|
|
2009
|
51 |
2 |
p. 297-302
6 p.
|
artikel
|
| 17 |
Immobilization of simulated evaporator concentrate waste in low density polyethylene
|
Cota, Stela
|
|
2009
|
51 |
2 |
p. 236-239
4 p.
|
artikel
|
| 18 |
Influence of evaluated data of fission product poisons on criticality
|
Ahmad, Ammar
|
|
2009
|
51 |
2 |
p. 334-338
5 p.
|
artikel
|
| 19 |
Lack of international consensus on the disposition and storage of disused sealed sources
|
Streeper, Charles
|
|
2009
|
51 |
2 |
p. 258-267
10 p.
|
artikel
|
| 20 |
Methods for determining operation life and reactivity depletion for space reactors with fast energy spectra
|
Schriener, Timothy M.
|
|
2009
|
51 |
2 |
p. 366-373
8 p.
|
artikel
|
| 21 |
Oxidation properties of Zr–Nb alloys at 973–1273K in air
|
Arima, Tatsumi
|
|
2009
|
51 |
2 |
p. 307-312
6 p.
|
artikel
|
| 22 |
Particle Swarm Optimization applied to the nuclear reload problem of a Pressurized Water Reactor
|
Meneses, Anderson Alvarenga de Moura
|
|
2009
|
51 |
2 |
p. 319-326
8 p.
|
artikel
|
| 23 |
Recent advances in nuclear power: A review
|
Abu-Khader, Mazen M.
|
|
2009
|
51 |
2 |
p. 225-235
11 p.
|
artikel
|
| 24 |
Recycling scheme and fuel cycle costs for twin BWRs reactors
|
Ramírez, José R.
|
|
2009
|
51 |
2 |
p. 303-306
4 p.
|
artikel
|
| 25 |
Spent fuel rod splitting due to UO2 oxidation during dry storage: Assessment of the database
|
Herranz, L.E.
|
|
2009
|
51 |
2 |
p. 201-206
6 p.
|
artikel
|
| 26 |
Sub-channel analysis of CANDU–SCWR and review of heat-transfer correlations
|
Yu, Jiyang
|
|
2009
|
51 |
2 |
p. 246-252
7 p.
|
artikel
|
| 27 |
The effect of carbon powder addition on the properties of hematite radiation shielding concrete
|
Kharita, M.H.
|
|
2009
|
51 |
2 |
p. 388-392
5 p.
|
artikel
|
| 28 |
Use of poly(methyl methacrylate) in radioactive waste management: I. Radiation stability and degradation
|
Özdemir, T.
|
|
2009
|
51 |
2 |
p. 240-245
6 p.
|
artikel
|
| 29 |
Virtual environments simulation for dose assessment in nuclear plants
|
Mól, Antônio Carlos A.
|
|
2009
|
51 |
2 |
p. 382-387
6 p.
|
artikel
|
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