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Featured researches published by Jianli Hao.


Science and Technology of Nuclear Installations | 2013

Effect of Heaving Movement on Flow Instability in U-Tubes of Marine Steam Generator under Natural Circulation

Jianli Hao; Wenzhen Chen; De Zhang

Under heaving movement conditions, the single phase flow instability in U-tubes is affected by the additional force, which will influence the marine reactor operation. In the present work, one-dimensional thermal-hydraulic model in U-tubes under heaving movement conditions is established, and the critical pressure drop (CPD) and critical mass flow rate (CMFR) which relate to the occurrence of reverse flow in U-tubes are proposed and analyzed. The effects of the heaving period and heaving acceleration amplitude on the flow instability in U-tubes with the different length are discussed. It is shown that (1) the CPD and CMFR are obviously affected by the heaving movement, which means that the reverse flow characteristic in U-tubes will be changed; (2) the fluctuation periods of the CPD and CMFR are the same as the heaving period, but the fluctuation magnitude of them is little affected by the heaving period; (3) the relative changes of CPD and CMFR are the linear function of heaving acceleration amplitude; and (4) the U-tube length has little influence on the relative changes of CPD and CMFR compared with the heaving acceleration amplitude, which means that the heaving movement has little influence on the space distribution of reverse flow in the U-tubes of marine steam generator.


Science and Technology of Nuclear Installations | 2013

A Study of Self-Burial of a Radioactive Waste Container by Deep Rock Melting

Wenzhen Chen; Jianli Hao; Zhiyun Chen

Aiming at the problem of radioactive waste disposal, the concept and mechanism of self-burial by deep rock melting are presented. The rationality and feasibility of self-burial by deep rock melting are analyzed by comparing with deep geological burial. The heat threshold during the process of contact melting around a spherical heat source is defined. The descent velocities and burial depths of spherical waste containers with varying radius are calculated. The calculated depth is much smaller than that obtained in the related literature. The scheme is compared with the deep geological burial that is currently carried out by the main nuclear countries. It is found that, at the end of melting, a radioactive waste container can reach deep strata that are isolated from groundwater.


18th International Conference on Nuclear Engineering: Volume 4, Parts A and B | 2010

Analysis of Single Phase Flow and Temperature Fields in Rectangular Channel With Translation in Width

Lei Luo; Wenzhen Chen; Zhiyun Chen; Jianli Hao

Plate fuel assemblies will be widely applied in the future because of their simple and compact structure and excellent heat exchange capability. When the plate fuel assemblies are used in a ship reactor, the effect of the ship motion on the reactor core thermal hydrodynamic must be investigated. In this paper, aiming at the rectangular shape of coolant channels in the assemblies, the numerical simulation of the flow and heat exchange in a rectangular channel in horizontal translation is carried out. Using the CFD Software and UDF code, the simulation model of the channel in horizontal translation with and without acceleration along its width direction is built up, and the related characteristics is analyzed and discussed. The results and conclusions are applicable and useful for the new type ship PWR design.Copyright


18th International Conference on Nuclear Engineering: Volume 2 | 2010

Study of the Space-Time Neutron Multiplication Formula

Jianli Hao; Wenzhen Chen; Shaoming Wang; De Zhang

The process of neutron multiplication is a discrete-time process, but the neutron transport theory takes neutron multiplication as a continuous neutron source, which ignores the discrete-time process of neutron multiplication, which would take in errors, so it is necessary for describing the process of neutron multiplication as a discrete-time process. “The neutron doubling formula including delayed neutrons” has been established which describes the process of neutron multiplication as a discrete-time process, but it has nothing to do with space. “The neutron doubling formula including delayed neutrons” could not be used to describe the variety of distributing of neutron density in transient process; it also could not be used to deal with the problem of three-dimensional space. In order to solve the problems mentioned above, the space-time neutron multiplication formula is established. Based on the theory of neutron multiplication, the concept of space is introduced to the neutron multiplication formula and the space-time neutron multiplication formula is established by taking into account of neutron transport. The formula can describe the inherent physical process of neutron multiplication in fission chain reaction system. The test of space-time neutron multiplication formula is done, which proves the formula is right. Given the initial neutron density as well as the multiplication factor, the formula can strictly describe the variety of neutron density (neutron flux density) with time. It could be used for setting a standard for estimating error for the measurement of neutron flux density as well as numerical calculation; the space-time neutron multiplication has larger applicability compared with the “neutron doubling formula including delayed neutrons”.Copyright


Annals of Nuclear Energy | 2013

Effect of U-tube length on reverse flow in UTSG primary side under natural circulation

Jianli Hao; Wenzhen Chen; De Zhang


Annals of Nuclear Energy | 2012

The development of fast simulation program for marine reactor parameters

Zhiyun Chen; Jianli Hao; Wenzhen Chen


Progress in Nuclear Energy | 2014

Flow instability analysis of U-tubes in SG based on CFD method

Jianli Hao; Wenzhen Chen; Shaoming Wang


Annals of Nuclear Energy | 2014

Scaling modeling analysis of flow instability in U-tubes of steam generator under natural circulation

Jianli Hao; Wenzhen Chen; De Zhang; Shaoming Wang


Annals of Nuclear Energy | 2012

The development of natural circulation operation support program for ship nuclear power machinery

Jianli Hao; Wenzhen Chen; Zhiyun Chen


Progress in Nuclear Energy | 2014

Analysis of reverse flow in U-tubes of UTSG in rocking motion

Xi Chu; Wenzhen Chen; Jianli Hao

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Wenzhen Chen

Naval University of Engineering

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De Zhang

Naval University of Engineering

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Xi Chu

Naval University of Engineering

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Zhiyun Chen

Naval University of Engineering

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Shaoming Wang

Naval University of Engineering

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Gaojie Hu

Naval University of Engineering

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L. Yu

Naval University of Engineering

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Lei Luo

Naval University of Engineering

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