[en] CH-HCSB TBM is designed to be tested in ITER by Southwestern Institute of Physics and its aim is to validate the feasibility of DEMO fusion reactor. The thermal-hydraulic safety analysis has to testify that the TBM and its Helium Cooling System (HCS) will not impact the safe operation of ITER under accidental conditions. In order to simulate the transient accidents, TBM and HCS are modeled using RELAP5. The steady state results indicate that the designed TBM input/output temperatures are obtained and the temperature of FW Beryllium armor is limited to the reasonable range. The Ex-Vessel LOCA is very dangerous because of the melting of FW Beryllium armor after about 80 seconds of the happened LOCA and some controlling measures have to be taken before melting. It's not so dangerous for the In-Vessel LOCA and In-Box LOCA, but the Tritium Extraction System has to be cut off from the HCS quickly when In-Box LOCA happens. Based on the results, the design of CH-HCSB TBM will be modified in order to assure the safety of TBM and ITER. (orig.)

[en] Chinese Helium Cooled Solid Breeder Test Blanket Module (CH-HCSB TBM) is designed to be tested in ITER and its aim is to validate its feasibility for DEMO fusion reactor. The thermal-hydraulic safety analysis has to testify that the TBM and its Helium Cooling System (HCS) will not influence the safe operation of ITER under normal and accidental conditions. In order to simulate the transient accidents and temperature evolution, the TBM and HCS are modeled using system code RELAP5/MOD3 and helium non-condensable gas model in the RELAP5/MOD3 is used to model the coolant. The Steady-State and three kinds of important Loss of Coolant Accidents (LOCA) have been analyzed. The Steady-State results indicate that the designed TBM inlet/outlet temperatures are obtained to be about 300/500 degree centigrade the design values. The temperature of First Wall beryllium armor is limited to the acceptable range. This means that the TBM structure and neutronics designs can satisfy the demand of thermal hydraulic design. The Ex-Vessel LOCA will induce the melting of First Wall beryllium armor after about 80 seconds of the LOCA initiation and some controlling measures have to be taken before melting. The pressurization of Vacuum Vessel induced by In-Vessel LOCA is within the allowable value of ITER design and will have little damage to TBM system and ITER. The In-Box LOCA would lead to pressurization of the TBM box, including all pebble beds and purge gas pipes to the system pressure of 8 MPa in about 2 seconds. So there must have a pressure relief for the blanket box, and at the same time the fast isolation of the Tritium Extraction System (TES) from TBM has to be taken to keep the TES safety. (author)

[en] Highlights: • This paper uses the portable decay gamma source feature in R2Smesh approach and proves that it is a versatile tool for the dose rate analysis. • The dose rates for ITER in-vessel components were calculated to check the R2Smesh portable decay gamma source feature. - Abstract: The R2Smesh (“Rigorous 2-step”) approach, developed by KIT for the determination of shut down dose rate distributions on high resolution mesh grids, can be utilized to calculate photon radiation dose fields around activated components which are moved from the irradiation site in ITER to some external location. In this work, the R2Smesh approach has been applied to dose rate analyses of various ITER in-vessel components of high complexity: A divertor cassette, four first wall modules, a generic diagnostic equatorial port plug and two test blanket modules. The considered components were first irradiated in ITER, and then moved to the transfer cask together with the associated decay gamma source distribution for the calculation of high resolution radiation dose fields in and around the transfer cask. The R2Smesh approach was shown to be a versatile tool for performing such analyses.

[en] Nuclear power plant has a high density of people, especially during construction. So it is important to evacuate nuclear plant workers safely and quickly in case of an emergency. From the angle of event-chain, firstly, the bus emergency dispatching decision-making procedure is analyzed; secondly, a general bus coordinated dispatching model for workers evacuation is established; and thirdly, an effective algorithm that is suitable to the on-line decision-making is put forward. The analysis of a practical example shows that the proposed method will decrease not only the time and cost in workers evacuation, but also the number of buses dispatched for the emergency evacuation. This optimum method could improve the efficiency and reliability of people evacuation in the nuclear power plant emergent event. (author)

[en] Objective: To evaluate the result of SPECT and CT in the patients with acute cerebral infarction and further more, to study the correlation between aphasia and dynamic change of regional cerebral blood flow (rCBF) in patients. Methods: Thirty cases with cerebral infarction of left basal ganglia were divided into two groups according to the presence or absence of aphasia; the vision and semi-ration analysis were used in photograph reading and region of interest (ROI) technology, respectively. Results: 1) Group A: there was a low rCBF in left basal ganglia, the dimension was larger than that in CT. There was also a low rCBF in frontal lobe and temporal lobe. Group B: there was only a low rCBF in left basal ganglia. 2) There were 6 cases with crossed cerebellar diaschisis (CCD) in the patients with aphasia. 3) The comparison about aphasia: the rCBF was higher in language center in the patients with improved language function than that in the patients without language function improvement and the difference between them was significant. Conclusions: The neurological function can be indirectly reflected through the study of the rCBF. At the same time, it may conduce to the locating of the damage in the central nervous system and to the differentiation diagnosis. It may also conduce to the programming of the therapeutic course and prognostication. (authors)

[en] Based on the Fusion-Driven Subcritical System (FDS-I), the 25 groups, 175 groups and 620 groups neutron nuclear data libraries with/without resonance self-shielding correction are made with the Njoy and Transx codes, and the K_eff and reaction rates are calculated with the Anisn code. The conclusion indicates that the resonance self-shielding effect affects the reaction rates strongly. (authors)

[en] A Hybrid Evaluated Nuclear Data Library (HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDLI1.0 contains one basic evaluated sub-library naming HENDL1.0/E and to processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing, distinguishing and choosing, HENDL1.0/E integrated basic evaluated neutron data files of 213 nuclides from the several main data libraries for evaluated neutron reaction cross sections including ENDF/B-VI (USA), JEF-2.2 (OECD/NEA, Europe), JENDL-3.2 (Japan), CENDL-2 (China), BROND-2 (Russia) and FENDL-2 (IAEA/NDS, ITER program). Based on this, 175-group neutron and 42-group photon neutron-photon coupled multi-group working library HENDL1.0/MG used for discrete ordinate Sn method transport calculation (such as ANISN code) and a compact ENDF form (ACE), continuous energy structure (pointwise) neutron cross section library HENDL1.0/MC for Monte Carlo method transport simulation (as MCMP code) can be attainable with the current group constants processing system NJOY and transport cross section preparation code TRANSX referring to the Vitamin-J energy group structure. In addition, two special bases i.e. transmutation (burnup) library BURNUP. DAT and response function library RESPONSE.DAT, have been also made for fuel cycle calculation and reactivity analyses of nuclear reactor. The relevant sample testing, benchmark checking and primary confirmation are also carried out to assess the validity of multi-purpose data library HENDL1.0. (authors)

[en] To meet the requirements of fusion-fission sub-critical hybrid reactor design and the other related studies, the evaluate nuclear data library named HENDL1.0/E has been constituted based on the several main national evaluated data libraries. The relevant working libraries including transport sub-libraries HENDL1.0/MG in groupwise form, HENDL1.0/MC in pointwise form, and the burnup sub-library HENDL1.0/BU and response function sub-library HENDL1.0/RF are generated using the nuclear data processing codes NJOY97 and TRANSX2. The simulating calculation and comparative analysis are carried out against a series of existing benchmark test experiments with popular neutron transport codes, in order to validate the correctness and availability of the HENDL1.0. (authors)

[en] The R2Smesh ('Rigorous 2-step') code system, developed by KIT for the determination of shut-down dose rate distribution on mesh grid, can be utilized to provide photon radiation dose field around activated components which are moved from the irradiation site in fusion reactor to another external location. R2Smesh couples MCNP transport calculations and FISPACT inventory calculations through suitable interfaces utilizing MCNP mesh tally capability. Neutron flux and the decay gamma source are provided with high resolution on the mesh grid superimposed to the real geometry to take into account the spatial variations of the flux and the decay gamma source distributions. This feature enables the decay gamma source distribution to be transferred from the irradiation site in the reactor to any other external location for the determination of photon flux and dose rate distributions. In this work, we applied the feature of the portable decay gamma source in R2Smesh code system to a dose rate analysis for a tunnel connecting the ITER tokamak complex building (TCB) and the hot cell facility building (HCFB). This paper presents the use of the portability feature of the decay gamma source in R2Smesh interface code system developed by KIT for a dose rate analysis of the ITER tunnel connecting TCB and HCFB. This application shows that the decay gamma source of the activated components could be transferred successfully from one coordinate system to another coordinate system and superimposed to the geometry of the components. This is very useful when the activated components need to be transported from the reactor to somewhere else for maintenance, testing or storage and the dose rate analysis is requested. Another portable feature, which could convert the 3D decay gamma source distribution generated by R2Smesh system to the MCNP 'SDEF' card source description and avoid the use of source sampling subroutine, is under consideration. With this feature, one decay gamma source result for the specific reactor components could be shared by different institutions who need to use the same decay gamma source for different analysis. (authors)

[en] Based on the mature technology of self-reliance 600 MW nuclear power plant design, and the construction feasibility study of large-scale underground nuclear power plants, the underground plant CUP600 with new models and technical scheme of independent intellectual property is developed and proposed for the first time in China, forming a complete set of engineering key technology. The evaluation demonstrates that the safety of this underground nuclear power plant is high, the construction technology is feasible, and the economy is reasonable with specific features of the fourth generation nuclear power technology, which fully meet the requirements of the latest nuclear safety standards of the state. (authors)