nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A central facility concept for nuclear microreactor maintenance and fuel cycle management
|
Fakhry, Faris |
|
|
56 |
3 |
p. 855-865 |
artikel |
2 |
Adsorption behavior of platinum-group metals and Co-existing metal ions from simulated high-level liquid waste using HONTA and Crea impregnated adsorbent
|
Osawa, Naoki |
|
|
56 |
3 |
p. 812-818 |
artikel |
3 |
Analysis of forced convection in the HTTU experiment using numerical codes
|
Potgieter, M.C. |
|
|
56 |
3 |
p. 959-965 |
artikel |
4 |
Analysis of the thermal-mechanical behavior of SFR fuel pins during fast unprotected transient overpower accidents using the GERMINAL fuel performance code
|
Dupont, Vincent |
|
|
56 |
3 |
p. 973-979 |
artikel |
5 |
Assessment of CATHARE code against DEC-A upper head SBLOCA experiments
|
Bousbia Salah, Anis |
|
|
56 |
3 |
p. 866-872 |
artikel |
6 |
Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor
|
Aufanni, Nariratri Nur |
|
|
56 |
3 |
p. 900-906 |
artikel |
7 |
Comparison on Safety Features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)
|
Takamatsu, Kuniyoshi |
|
|
56 |
3 |
p. 832-845 |
artikel |
8 |
Conceptual design of a MW heat pipe reactor
|
Wu, Yunqin |
|
|
56 |
3 |
p. 1116-1123 |
artikel |
9 |
Consequence-based security for microreactors
|
Gateau, Emile |
|
|
56 |
3 |
p. 1108-1115 |
artikel |
10 |
Core design study of the Wielenga Innovation Static Salt Reactor (WISSR)
|
Wielenga, T. |
|
|
56 |
3 |
p. 922-932 |
artikel |
11 |
Cross section generation for a conceptual horizontal, compact high temperature gas reactor
|
Kang, Junsu |
|
|
56 |
3 |
p. 933-940 |
artikel |
12 |
Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production
|
Kim, Ji Yong |
|
|
56 |
3 |
p. 1037-1051 |
artikel |
13 |
Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions
|
Kubo, Yoshihiro |
|
|
56 |
3 |
p. 846-854 |
artikel |
14 |
Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers
|
Wang, Xicheng |
|
|
56 |
3 |
p. 1052-1065 |
artikel |
15 |
Evaluation of temperatures and flow areas of the Phebus Test FPT0
|
Nishida, Koji |
|
|
56 |
3 |
p. 886-892 |
artikel |
16 |
Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor
|
Choi, Won Jun |
|
|
56 |
3 |
p. 1002-1012 |
artikel |
17 |
Fundamental evaluation of hydrogen behavior in sodium for sodium-water reaction detection of sodium-cooled fast reactor
|
Yamamoto, Tomohiko |
|
|
56 |
3 |
p. 893-899 |
artikel |
18 |
Idaho national laboratory to demonstrate collaboration first versus competition to accelerate achieving a secure clean energy future by 2031
|
Kandasamy, Jhansi |
|
|
56 |
3 |
p. 966-972 |
artikel |
19 |
Multi-batch core design study for innovative small modular reactor based on centrally-shielded burnable absorber
|
Wijaya, Steven |
|
|
56 |
3 |
p. 907-915 |
artikel |
20 |
Nodal method for handling irregularly deformed geometries in hexagonal lattice cores
|
Kim, Seongchan |
|
|
56 |
3 |
p. 772-784 |
artikel |
21 |
Nuclear waste attributes of near-term deployable small modular reactors
|
Kim, Taek K. |
|
|
56 |
3 |
p. 1100-1107 |
artikel |
22 |
Numerical analysis of the venturi flowmeter in the liquid lead-bismuth eutectic circuit after long-term operation
|
Zhang, Zhichao |
|
|
56 |
3 |
p. 1081-1090 |
artikel |
23 |
NUWARD SMR safety approach and licensing objectives for international deployment
|
Francis, D. |
|
|
56 |
3 |
p. 1029-1036 |
artikel |
24 |
Overview of separate effect and integral system tests on the passive containment cooling system of SMART100
|
Yang, Jin-Hwa |
|
|
56 |
3 |
p. 1066-1080 |
artikel |
25 |
PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems
|
Montout, Michaël |
|
|
56 |
3 |
p. 803-811 |
artikel |
26 |
Radiation effect on the corrosion of disposal canister materials
|
Lee, Minsoo |
|
|
56 |
3 |
p. 941-948 |
artikel |
27 |
Rare earth removal from pyroprocessing fuel product for preparing MSR fuel
|
Yoon, Dalsung |
|
|
56 |
3 |
p. 1013-1021 |
artikel |
28 |
Sensitivity of a control rod worth estimate to neutron detector position by time-dependent Monte Carlo simulations of the rod drop experiment
|
Park, Jong Min |
|
|
56 |
3 |
p. 916-921 |
artikel |
29 |
SIMMER-IV application to safety assessment of severe accident in a small SFR
|
Tagami, H. |
|
|
56 |
3 |
p. 873-879 |
artikel |
30 |
SiRENE: A new generation of engineering simulator for real-time simulators at EDF
|
Pialla, David |
|
|
56 |
3 |
p. 880-885 |
artikel |
31 |
Special Issue on the International Congress on Advances in Nuclear Power Plants (ICAPP2023)
|
Ha, Jaejoo |
|
|
56 |
3 |
p. 771 |
artikel |
32 |
SSC risk significance in risk-informed, performance-based licensing of non-LWRs
|
Lin, James C. |
|
|
56 |
3 |
p. 819-823 |
artikel |
33 |
Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
|
An, Hyo Jun |
|
|
56 |
3 |
p. 949-958 |
artikel |
34 |
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
|
Ju, Kwangho |
|
|
56 |
3 |
p. 1022-1028 |
artikel |
35 |
The development of a fuel lifecycle reactivity control strategy for a generic micro high temperature reactor
|
Atkinson, Seddon |
|
|
56 |
3 |
p. 785-792 |
artikel |
36 |
Thermal dehydration tests of FLiNaK salt for thermal-hydraulic experiments
|
Che, Shuai |
|
|
56 |
3 |
p. 1091-1099 |
artikel |
37 |
Thermal study of the emergency draining tank of molten salt reactor
|
Péniguel, C. |
|
|
56 |
3 |
p. 793-802 |
artikel |
38 |
The SPIZWURZ project – Experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions
|
Grosse, Mirco |
|
|
56 |
3 |
p. 824-831 |
artikel |
39 |
The TANDEM Euratom project: Context, objectives and workplan
|
Vaglio-Gaudard, C. |
|
|
56 |
3 |
p. 993-1001 |
artikel |
40 |
Transient full core analysis of PWR with multi-scale and multi-physics approach
|
Lee, Jae Ryong |
|
|
56 |
3 |
p. 980-992 |
artikel |