[en] SDC Update: - The revised SDC report (Rev.1) submitted to EG members of GIF in October 2017. - The original SDC report was delivered to external entities for review such as national nuclear regulators and international organization in 2013. - The SDC TF received the comments from China's NNSA, USNRC, IAEA and IRSN. SDC TF has produced the revision of SDC as well as the resolution documents that include the response to the comment. - The revised SDC also reflects the revision of IAEA SSR 2/1.

No abstract available

[en] Cold trap performance conformed to an empirical model for hydrogen removal during trapping of the first 75% of the hydrogen removed. 1 ref

[en] A computer model is being developed to optimize cold trap design for hydrogen capacity. Hydrogen mass transfer coefficients ranging upward from 6*10/sup -5/ m/s were measured. The rate of mass transfer and the efficiency of the trap increased with increasing quantities of NaH deposited. 14 refs

No abstract available

[en] Summary: • Two kinds of design concepts were proposed. They have FTA and MTA with sufficient flux level. Three separate FTL can be installed for various experiments. Flux level at MTA was less than goal of 3.0 n/cm²-sec . Power rating of 100MWe should be increased. (150MWe). • All safety parameters are satisfied with conventional requirements

[en] The invention applies more particularly to integrated type reactors cooled by liquid sodium. The roof slab comprises a first central annular part of which the diameter is nearly equal to the diameter of the main vessel and a second outlying annular part linked to the first one by its external ring. The two parts are made to form an annular steel box filled with concrete. The central part is reinforced by two truncated shells. The outlying part is reinforced by planar radial shells. The internal shell of the second part constitutes the external shell of the central part. This roof slab is resistant to the reactor temperature variations and to earthquakes in good conditions

[en] Inspection in opaque liquid metal coolant is one of important issues for sodium-cooled fast reactors. To facilitate operations and maintenance activities, various under sodium viewers (USVs), including horizontal USVs for obstacle detection for a long distance and imaging USVs for a short and middle distance imaging, have been developed in several research institutes and countries. In this study, an imaging USV for a middle distance, approximately 1 m, has been developed. The USV in this study adopts an optical receiving system which measures the vibration displacement of diaphragm by using a laser as a receiving sensor. This study mainly focuses on the sensitivity improvement for a transmission sensor and the receiving sensor. In addition, an imaging experiment in the water was conducted using the new transmission sensor and receiving sensor. The experimental results showed that the newly developed USV sensors can make higher resolution images of a target than the previous sensors. (author)

[en] The conceptual designs of a SFR (sodium-cooled Fast Reactor) and key technological developments were promoted through the Korea national long term R and D projects. The conceptual design of a SFR demonstration reactor of 600MWe capacity has been developed in 2012 through the project by KAERI. The preliminary general arrangement of reactor building and fuel building have performed taking into account of the layout criteria of main systems, components, transport of equipment, and accessing paths to core assemblies inside the buildings. In this paper, firstly the design concept of the SFR fuel building was explained. Second, the layouts of the main systems, equipment, and wall compartments are shortly described. Third, the import and export paths of the core assemblies to and from the fuel handling and storage buildings are represented and the vertical height variations of the paths are figured out to exam any technical issues. Finally, a three-dimensional conceptual solid model of the fuel handling and storage building was built for checking design availability

[en] In order to meet the rising energy demand and the emission of greenhouse gas, the generation IV International Forum is undertaking the development of innovative nuclear energy system with the goals, safety, economics, resource utilization, waste management, proliferation resistance and physical protection (PR and PP). The sodium-cooled Fast reactor (SFR) system is among the six systems selected for Gen-IV promising systems and expected to be deployed in 2020. Since 1997, R and D on SFR has been actively launched as a part of the national long-term nuclear R and D program. And the Korea Advanced Liquid Metal Reactor (KALIMER) developed in Korea was chosen as a GEN-IV SFR reference reactor. In the end of 2008, the 255^th Atomic Energy Commission finalized the SFR R and D roadmap to construct the demonstration reactor by 2028. International collaborative research is under way on fuel developments within Advanced Fuel Project for Gen-IV SFR with the closed fuel cycle of full actinide recycling, while TRU bearing metallic fuel, U-TRU-Zr alloy fuel, was selected and is being developed at KAERI in conjunction with a pyroprocessing technology. In this paper, in order to develop the process requirements and design the process technology for the fabrication of TRU bearing metallic fuel, the fabrication process flow and key process technologies were assessed and evaluated