[en] It gives a contrast of the principles, methods, advantages and disadvantages of nuclear detector in X-γ radiation monitoring, and brief introduction of the range of different applications of X-γ radiation dose rate meter and purchase points in order to bring more reference value on purchase, use and maintenance the nuclear detector for monitoring personal. (authors)

[en] The HT-7U superconducting tokamak will generate neutrons at a rate of the order of 10¹⁵ per second during the D-D operation with long pulse up to 1000 s. Nuclear heat in the Toroidal Field (TF) and Poloidal Field (PF) coils have been estimated by using the Monte Carlo particle transport code MCNP-4C and the latest version of the Fusion Evaluated Nuclear Data Library (FENDL-2) based on the three-dimensional geometrical configuration. The calculations show that the nuclear heat in the coils originates ∼10% from neutron energy deposition and ∼90% from induced gamma energy deposition. To reduce the nuclear heat in the superconducting magnets of the TF and PF coils, a double-wall-structured vacuum vessel (VV) with the boronated water layer of thickness of 5 cm is designed to shield against neutron irradiation

[en] It is very important for transmutation of long-lived fission products (LLFP) due to the serious radioactive hazard of the LLFP from commercial fission reactors. Considering the developing level of LLFP isotopic separation technology, the chemical forms for transmutation of ⁹⁹Tc, ¹²⁹I and ¹³⁵Cs are presented. This paper discussed the transmutation effect of the different moderators on the burning efficiency. The dedicated dual-cooled long-lived radioactive waste transmutation blanket (DWTB) for the Fusion-Driven Subcritical system (FDS) has been considered to transmute LLFP. As the part of the DWTB conceptual design, the optimized LLFP compositions and form designs have been done to improve the performance of LLFP transmutation. Neutronics optimal calculation about LLFP transmutation has been carried out to compare the performances of different LLFP transmutation designs. (authors)

[en] In this paper, the source-free efficiency calibration method is used to verify the HPGe γ-spectrometer. A ⁶⁰Co standard point source and three body sources were used in the efficiency calibration with the LabSOCS code. The results show that this method can be used as a supplement method to efficiency calculation and laboratory quality control. Meanwhile, the impact factors of source-free efficiency fitting were analyzed. (authors)

[en] This paper outlined current regulations and standards on NPP radioactive effluents monitoring in China. Combined with NPP environmental monitoring practices over the years in Jiangsu Province, problems existed in the process of supervisory monitoring were discussed. The author proposed such as the establishment of guidelines on supervisory monitoring of radioactive effluents, emission standards for outflow concentration, effluent monitoring laboratories, continuous monitoring system for seawater to regulate radioactive effluents supervisory monitoring in NPPs and provide technical support to the government's supervision and environmental management ensuring the safety of public and environment around the nuclear power sites. (authors)

[en] HPGe γ spectrometry sourceless efficiency calibration method is playing an important role in radioactive analysis, for its high accuracy and efficiency, can be used without radioactive source, facilitated in situ measurement. By verification with the IAEA reference materials, we verified the reliability of γ spectrometry sourceless efficiency calibration. And using this method, we analyzed the radioactive nuclides in rare earth residues of our province. The result shows that, the radioactive equilibrium among the parents and the daughters in uranium (thorium) decay series of the rare earth residues has been destroyed and radioactivity level has obvious difference. Based the results, this paper investigates and analyses the radioactive residues of rare earth smelting and separation plants in Jiangsu Province, and puts forward some suggestions on volume reduction. (authors)

[en] The present situation of NORM residues arising from rare earths extraction and separation in Jiangsu Province has been investigated comprehensively. The management of these residues is discussed and analysed with respect to the separation technology, the activity concentrations, the amounts of residue generated and the regional eco-environmental features. Some conclusions and suggestions on the disposal of these NORM residues are given, with reference to the relevant national laws, regulations and standards. (author)

[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] 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] Calculations and analysis on the fusion-driven sub-critical system FDS have been performed. Neutronics calculations have been done with the multi-functional code VisualBUS1.0 and the data library HENDL1.0/MG to obtain the neutron spectra of different regions of the blanket of FDS-I. Then activation calculations of structural steel CLAM, tritium breeding material/coolant LiPb etc. and the impurities controlling level for CLAM and LiPb were carried out with the code FISPACT and the IAEA activation data library FENDL/A-2.0. (authors)