[en] Inspection and repair of tower structure and lift, instrument calibration have been done in the scope of 'Environmental Radiation Monitoring Around the Nuclear Facilities' project. Wind direction, wind speed, temperature, humidity at 67m, 27m, and 10m height and temperature, humidity, atmospheric pressure, solar radiation, precipitation, and visibility at surface have been measured and analyzed with statistical methods. At the site, the prevailing wind directions were E in spring and summer, NNW in winter season. The calm distributed 27.3% at 67m, 37.4% at 27m, 52.2% at 10m height. Wireless data transmission to MIPS(Meteorological Information Processing System) has been done after collection in the DAS where environmental assessment can be done by the developed simulation programs in both cases of normal operation and emergency

[en] All radioisotope transport packages are imported from abroad. The objective of this study is to develop the RI transport package combining transportable and economical efficiencies. This report describes the objective of project, necessaries, state of related technology, scope and results, proposal for application etc. The scope of the project consist of safety evaluation of medical RI package, preliminary safety evaluation of industrial RI package and evaluation for application of high efficiency shielding material

[en] The objective of this project is development of RI transport package and establishment of transportation system. This report describes the objective of project, necessaries, state of related technology, scope and results, proposal for application etc. The scope of the project consist of establishment of performance test system for type-A package for medical use, development of type-B package for industrial use and development of casting technology for DU shield and evaluation of shielding efficiency. The research results obtained from this project are expected to be utilized as a basic data for design, analysis, test and license of transport package

[en] In the field of high speed crash, the system for practicing the aircraft crash safety evaluation through computer simulation for the storage system of spent nuclear fuel was presented. In the field of transient fire, the computer simulation method for transient fire was drawn through the overseas status and methodology analysis. In the field of cumulative condition for transport accident, the analysis technique for assessment for cumulative effects which is occurred from successive accident conditions was developed and proposed. The development plan for the PSA tool which is comprised of modules such as project tree module, system description, hazard analysis module, frequency analysis module was established by using the event tree analysis and fault tree analysis, consequence analysis module for the estimation of exposure doses for workers and the general public

[en] The KMP and MBA was determined on the basis of the design of the containment and surveillance for the ACP facility. It was indicated from the safeguard ability evaluation that the pilot-scaled ACP facility is safeguardable. The prototype ASNC is composed of 20 Cd plate-attached He-3 tubes embedded in a high density PE cylinder containing a cavity of 10 cm in radius and a lead shield in its inside respectively and having a carbon neutron reflector on the top and bottom of the cylinder. The average and standard error of the neutron detection efficiency at 20 cm height are 19 % and 2 %, respectively, which satisfies the design requirements of 14 % efficiency and 2 % error. In the results of the integration analysis for the dry storage of the conditioned spent fuel, the vault type was found to be more profitable than the metal cask type, so the vault type was selected with the optimum storage system for the conditioned spent fuel. For a study of the efficient storage, the exponential decay constant for the PWR spent fuel is measured using the exponential experiment system installed in the KAERI PIEF. The neutron effective multiplication factor which is determined on the basis of the constant is shown to be roughly consistent with the calculated keff with the MCNP code. U-Nb binary alloy shows its oxidation rates one order of a magnitude less than that of the unalloyed uranium. The results from this study are applicable to the optimum stability method of the conditioned spent fuel

[en] A shipping package needs to safely transport from producing center to consuming center. The shipping package has to be met for conditions as prescribed by law. Radioactive isotope is used as liquid form or capsule form. A Type A package, which is to transport liquid radioactive materials, has to maintain the structural integrity for the condition of 9 m free drop. The Type A Package shall be provide with a containment system composed of primary inner and secondary outer containment components or shall be provided with sufficient absorbent material to absorb twice the volume of the liquid contents. Accordingly, a shock absorber material and an absorbent material to apply to the shipping package, which is to transport liquid radioactive isotope, was estimated

[en] This is contract result report conducted by KAERI under the contract with NETEC for structural and thermal evaluation of dry storage system for spent nuclear fuel. This report contains the thermal, structural and seismic tests and analyses for verification of safety evaluation for storage cask. Thermal tests for storage cask were conducted under normal, off-normal and accident conditions. There were good agreements between the thermal analysis and test results. Structural tests were conducted under drop and turn-over conditions. The measured strain and acceleration from the tests are slightly lower than the analysis results. The results of the seismic test also accord with the analysis results. Therefore, it was shown that the analysis method and procedure were successfully established to evaluated the safety for the storage cask. Safety analysis procedures has been established to evaluate the thermal, structural and seismic safeties of storage cask

[en] In the transportation and storage characteristics analysis of the pyroprocess materials, the radioactivity, heat generation and yield of the materials are examined and from the information a new concepts of canisters have been developed. The optimized capacity, transportation frequency and operation period of pyroprocess facility are found using the logistics analysis program developed in this project. Through the safety analysis for the hot cell transportation system, it has been found that the newly developed system complies with the related regulations for the transportation of high level radioactive materials. The shielding, criticality, structural and thermal performance of the hot cell transportation system are evaluated using computational analyses and verified by the tests using a 1/2 scale model. This data can be usefully utilized in the license acquisition process for the system. A new type hot cell docking system with superior performance compared to the existing one has been developed with a patented rotating lid system. In the design of interim storage system for the pyroprocess material, various aspects should be taken into account such as the shielding, containment performance, heat removal, management and economic aspects related with storage of various radionuclides. We have reached to a unique concept of interim storage of pyroprocess materials and selected a system through a comparative evaluation of existing ones

[en] The objectives of this project is to develop an spent fuel characteristic analyzing equipment and characteristic parameters measuring technology for the advanced spent fuel management process which converts a spent fuel into the metallic ingot for storage. The contents and scope of this project are under-water burn-up measuring technology, surface micro structure and analysis for spent nuclear fuels, dimensional measurement technology for spent fuel assemblies and internal pressure and fission gas measuring system for spent fuel rod. The under-water burn-up determination algorithm was developed and improved by the measuring test. The system was verified within a tolerance of 5%. The surface micro structure and analysis system for spent fuels was established by the development of a shielded glove box and hot-cell specimen cask. The modified SEM was installed in the shielded glove box. The dimensional measuring algorithm by using the image process method was developed and verified by the performance test using simulated fuel rods. Internal pressure and fission gas measuring was developed and finished performance test. The results of this project will be used for verification of the advanced spent fuel management process

[en] In the first stage of the research, the transportation and storage characteristics analysis of the pyroprocess materials, the development of horizontal type hot cell transportation system, and the design of interim storage system for the pyroprocess material are conducted. The optimized capacity, transportation frequency and operation period of pyroprocess facility are found using the logistics analysis program developed in this project. A new hot cell transportation system was designed. Through the safety analysis and test for the hot cell transportation system, the design license has been approved. A new type hot cell docking system with superior performance has been developed with a patented rotating lid system. We have reached to a unique concept of interim storage of pyroprocess materials and selected a system through a comparative evaluation of existing ones. In the second stage of the research, transportation/storage/sealing devices for PRIDE recovered material/wastes were developed. And test model for the devices in engineering scale facility were also developed. The design requirements for a vertical docking system were evaluated and the performance assessment using a scaled mock-up was conducted. Integrated storage management technology was evaluated for an efficient management of process materials. A heat transfer simulation and characteristics analysis for the storage system were conducted. The derivation of design requirements, design and fabrication of a canister test model, and preliminary safety assessment were conducted