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                             40 gevonden resultaten
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
                             40 gevonden resultaten
 
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