[en] A full scale hot testing facility is built up to test the main equipment of the fuel circulating system and control system of the 10 MW high temperature gas cooled reactor (HTR-10) in real operating temperature and helium of the reactor and to gain designing and operating experience. OMRON C200H PLC and a mosaic simulation pane are used in the control system. The operation status of the system is controlled and monitored by the computer. All the designing and operating experience have been applied to the construction design of HTR-10

[en] The author discusses on the necessity of carrying out regularization control in designing and constructing the 10 MW high temperature gas-cooled reactor (HTR-10), from the requirement of nuclear safety, of technical feasibility, of economical feasibility and accumulating developmental experiences. The author expounds taking some effective measures in the practice of carrying out regularization control on HTR-10. These measures include laying down design control procedures, working out HTR-10 design criteria according to current codes and standards, carrying on regularization design, regularization control of design documents and drawings, and according to quality assurance programs and procedures carrying on regularization control, for ensuring engineering progress and quality. It has universality for regularization control of nuclear engineering projects design and construction. The author also provides some beneficial use of reference for later nuclear engineering design and construction

[en] The 10 MW high temperature cooled reactor (HTR-10) built in Tsinghua University is a pebble bed type of HTGR. The continuous recharge and multiple-pass of spherical fuel elements are used for fuel management. The initiative stage of core is composed of the mix of spherical fuel elements and graphite elements. The equilibrium stage of core is composed of identical spherical fuel elements. The fuel management during the transition from the initiative stage to the equilibrium stage is a key issue for HTR-10 physical design. A fuel management strategy is proposed based on self-adjustment of core reactivity. The neutron physical code is used to simulate the process of fuel management. The results show that the graphite elements, the recharging fuel elements below the burn-up allowance, and the discharging fuel elements over the burn-up allowance could be identified by burn-up measurement. The maximum of burn-up fuel elements could be controlled below the burn-up limit

[en] Through the project experiential introduction about HTR-10 high temperature gas-cooled reactor, the realistic significance about HTR-10 success to high temperature gas-cooled reactor demonstration project has been expatiated. (authors)

[en] The 10 MW high temperature gas cooled reactor (HTR-10) was built at Institute of Nuclear Energy Technology, Tsinghua University, and the first criticality was attained in Dec. 2000. The high temperature gas cooled reactor physics simulation code VSOP was used for the prediction of the fuel loading for HTR-10 first criticality. The number of fuel element and graphite element was predicted to provide reference for the first criticality experiment. The prediction calculations toke into account the factors including the double heterogeneity of the fuel element, buckling feedback for the spectrum calculation, the effect of the mixture of the graphite and the fuel element, and the correction of the diffusion coefficients near the upper cavity based on the transport theory. The effects of impurities in the fuel and the graphite element in the core and those in the reflector graphite on the reactivity of the reactor were considered in detail. The first criticality experiment showed that the predicted values and the experiment results were in good agreement with little relative error less than 1%, which means the prediction was successful

[en] The 10 MWth high-temperature gas-cooled test reactor (termed HTR-10) went into criticality at the Institute of Nuclear Energy Technology (INET) of Tsinghua University in December 2000. As required by China nuclear safety authorities, we had developed nuclear emergency response plan and relevant technical procedures for the implementation of protective actions should an accident occur. This paper presents the technical basis for the development of the HTR-10 nuclear emergency plan. Firstly, it describes briefly the requirements of the China nuclear safety authorities about the nuclear emergency planning and preparedness for research reactors. Then, the paper focuses on the technical development of initiating conditions (ICs) and emergency action levels (EALs) for HTR-10. The ICs and EALs developed are tabulated in this paper. Finally, a brief presentation about the on-site emergency response exercise carried out before the first fuel loading on HTR-10 and other emergency preparedness activities conducted or being planned are given in this paper. (author)

[en] This paper discusses the historical development of the high temperature gas cooled reactor (HTGR) in China. China's development strategy of the HTGR will be explained in this text. The aim, design, construction and commissioning of the 10 MW HTGR--test module (HTR-10) will be explained herein. The engineering experiments, which were developed for the HTR-10, will also be introduced. The experience leading to an accumulation of knowledge during the development of China's HTGR will be summarized in this article

[en] The helium circulator is a key component of 10 MW high temperature gas-cooled reactor (HTR-10), which has the helium coolant circulate inside the primary loop of the reactor. Before delivery, the performance experiment of the circulator was carried out in the factory at 0.426 MPa, 250 deg. C nitrogen condition. In the paper, by using dimensional methodology, the experiment results are converted to those on 3.0 MPa, 250 deg. C helium condition which is real working condition on the reactor. Then the circulator performances are analyzed. Finally, the operating performances on HTR-10 are predicted. The paper concludes that the circulator design was made correctly and the performances are satisfied with HTR-10 operating requirements

[en] Highlights: • A coaxial stacking disjoint model of HTR-10 is studied. • The mathematic geometrical relationships about the model are studied in detail. • This model can achieve accurate initial criticality value of HTR-10 reactor. - Abstract: HTR-10 is quite different than conventional reactors due to its geometry, spherical fuel elements and random distribution of fuel elements and graphite balls. It is desired to built realistic and accurate reactor model. In this paper, the detailed mathematic geometrical relationships of HTR-10 are studied on HTR-10′s coaxial stacking disjoint model. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by SuperMC. Compared with available data, this model can achieve accurate results in terms of initial criticality of the HTR-10 reactor.

No abstract available