nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Analysis of C5G7-TD benchmark with a multi-group pin homogenized SP3 code SPHINCS
|
Cho, Hyun Ho |
|
|
53 |
5 |
p. 1403-1415 |
artikel |
2 |
Antecedents of self-reported safety behaviors among commissioning workers in nuclear power plants: The roles of demographics, personality traits and safety attitudes
|
Tao, Da |
|
|
53 |
5 |
p. 1454-1463 |
artikel |
3 |
Applicability of the induction bending process to the P91 pipe of the PGSFR
|
Kim, Nak Hyun |
|
|
53 |
5 |
p. 1580-1586 |
artikel |
4 |
A study on the dynamic characteristics of the secondary loop in nuclear power plant
|
Zhang, J. |
|
|
53 |
5 |
p. 1436-1445 |
artikel |
5 |
Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation
|
Asal, Sinan |
|
|
53 |
5 |
p. 1634-1641 |
artikel |
6 |
BOTANI: High-fidelity multiphysics model for boron chemistry in CRUD deposits
|
Seo, Seungjin |
|
|
53 |
5 |
p. 1676-1685 |
artikel |
7 |
CATHARE simulation results of the natural circulation characterisation test of the PKL test facility
|
Bousbia Salah, Anis |
|
|
53 |
5 |
p. 1446-1453 |
artikel |
8 |
Development and strengthening of the nuclear and radiation safety infrastructure for nuclear power program of Bangladesh
|
Islam, Md. Shafiqul |
|
|
53 |
5 |
p. 1705-1716 |
artikel |
9 |
Development of a truncation artifact reduction method in stationary inverse-geometry X-ray laminography for non-destructive testing
|
Kim, Burnyoung |
|
|
53 |
5 |
p. 1626-1633 |
artikel |
10 |
Dissolution behavior of SrO into molten LiCl for heat reduction in used nuclear fuel
|
Kang, Dokyu |
|
|
53 |
5 |
p. 1534-1539 |
artikel |
11 |
Effect of different tungsten compound reinforcements on the electromagnetic radiation shielding properties of neopentyl glycol polyester
|
Can, Ömer |
|
|
53 |
5 |
p. 1642-1651 |
artikel |
12 |
Effects of 3D contraction on pebble flow uniformity and stagnation in pebble beds
|
Wu, Mengqi |
|
|
53 |
5 |
p. 1416-1428 |
artikel |
13 |
Enhanced mechanical properties and interface structure characterization of W–La2O3 alloy designed by an innovative combustion-based approach
|
Chen, Pengqi |
|
|
53 |
5 |
p. 1593-1601 |
artikel |
14 |
Enhancing utilization and ensuring security: Insights to compromise contradicting conditions in new research reactors
|
Alrammah, Ibrahim |
|
|
53 |
5 |
p. 1479-1482 |
artikel |
15 |
Evaluation of decontamination factor of radioactive methyl iodide on activated carbons at high humid conditions
|
Choi, Byung-Seon |
|
|
53 |
5 |
p. 1519-1523 |
artikel |
16 |
Fuzzy FMECA analysis of radioactive gas recovery system in the SPES experimental facility
|
Buffa, P. |
|
|
53 |
5 |
p. 1464-1478 |
artikel |
17 |
Illustration of Nagra’s AMAC approach to Kori-1 NPP decommissioning based on experience from its detailed application to Swiss NPPs
|
Volmert, Ben |
|
|
53 |
5 |
p. 1491-1510 |
artikel |
18 |
Influence and analysis of a commercial ZigBee module induced by gamma rays
|
Shin, Dongseong |
|
|
53 |
5 |
p. 1483-1490 |
artikel |
19 |
Investigation on the effect of eccentricity for fuel disc irradiation tests
|
Scolaro, A. |
|
|
53 |
5 |
p. 1602-1611 |
artikel |
20 |
Material attractiveness of unirradiated depleted, natural and low-enriched uranium for use in radiological dispersal device
|
Ahn, Jihyun |
|
|
53 |
5 |
p. 1652-1657 |
artikel |
21 |
Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors
|
Wang, Haoran |
|
|
53 |
5 |
p. 1569-1579 |
artikel |
22 |
Monte Carlo simulation for verification of nonparametric tests used in final status surveys of MARSSIM at decommissioning of nuclear facilities
|
Sohn, Wook |
|
|
53 |
5 |
p. 1664-1675 |
artikel |
23 |
Neuro-fuzzy modeling of deformation parameters for fusion-barriers
|
Akkoyun, Serkan |
|
|
53 |
5 |
p. 1612-1618 |
artikel |
24 |
Neutron imaging for metallurgical characteristics of iron products manufactured with ancient Korean iron making techniques
|
Cho, Sungmo |
|
|
53 |
5 |
p. 1619-1625 |
artikel |
25 |
Numerical analysis of the temperature distribution of the EM pump for the sodium thermo-hydraulic test loop of the GenIV PGSFR
|
Kwak, Jaesik |
|
|
53 |
5 |
p. 1429-1435 |
artikel |
26 |
Radioiodine removal from air streams with impregnated UVIS® carbon fiber
|
Obruchikov, Alexander V. |
|
|
53 |
5 |
p. 1717-1722 |
artikel |
27 |
Research on the impact effect of AP1000 shield building subjected to large commercial aircraft
|
Wang, Xiuqing |
|
|
53 |
5 |
p. 1686-1704 |
artikel |
28 |
Second order of average current nodal expansion method for the neutron noise simulation
|
Poursalehi, N. |
|
|
53 |
5 |
p. 1391-1402 |
artikel |
29 |
Structural stability analysis of waste packages containing low- and intermediate-level radioactive waste in a silo-type repository
|
Byeon, Hyeongjin |
|
|
53 |
5 |
p. 1524-1533 |
artikel |
30 |
Study of neutron energy and directional distribution at the Beloyarsk NPP selected workplaces
|
Pyshkina, Mariia |
|
|
53 |
5 |
p. 1723-1729 |
artikel |
31 |
The evolution of radiation-induced point defects near symmetrical tilt Σ5 (310) <001> grain boundary in pure δ-plutonium: A molecular dynamics study
|
Wang, Yangzhong |
|
|
53 |
5 |
p. 1587-1592 |
artikel |
32 |
The Pahlev Reliability Index: A measurement for the resilience of power generation technologies versus climate change
|
Norouzi, Nima |
|
|
53 |
5 |
p. 1658-1663 |
artikel |
33 |
Thermal behavior of groundwater-saturated Korean buffer under the elevated temperature conditions: In-situ synchrotron X-ray powder diffraction study for the montmorillonite in Korean bentonite
|
Park, Tae-Jin |
|
|
53 |
5 |
p. 1511-1518 |
artikel |
34 |
Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology
|
Li, Yuanming |
|
|
53 |
5 |
p. 1540-1555 |
artikel |
35 |
Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics
|
Li, Yuanming |
|
|
53 |
5 |
p. 1556-1568 |
artikel |