Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly

Liu, X.J.; Xu, Cheng

doi:10.1016/j.anucene.2008.11.001

Cited by 47 publications

(9 citation statements)

References 5 publications

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“…Shanghai Jiao Tong University (SJTU) proposed design for thermal neutron spectrum SCWR (Liu and Cheng, 2009) along with European design of High Performance Light Water Reactor (HPLWR) (Squarer et al, 2003) clearly stand out among other thermal spectrum SCWR designs (MacDonald, 2005;Yamaji et al, 2005). Both, SJTU proposed design and HPLWR design, concepts show good neutron physics and thermal hydraulics characteristics.…”

Section: Studied Fuel Assemblymentioning

confidence: 95%

“…A reasonable percentage of thermal neutrons, which ensures flatter radial power density and hence avoids the use of many different enrichment fuel pins in single fuel assembly, is one design goal. The additional design criteria required for SCWR are Linear Heat Generation Rate (LHGR) should be less than or equal to 39 kW/m to keep fuel temperature in safe limits (Oka et al, 2010) Maximum Clad Surface Temperature (MCST) should be less than 650 C when using nickel based alloy clad and structural material (Oka et al, 2010) Current analyses are performed without any alteration to fuel assembly original design (Liu and Cheng, 2009). Design parameters used for current study are given in Table 1 (Liu and Cheng, 2009).…”

Section: Studied Fuel Assemblymentioning

confidence: 99%

“…MCNP code offers the benefits of detailed geometry modeling capabilities along with continuous energy treatment. Pseudo material construct (Conlin et al, 2005) Table 1 Design parameters for reference fuel assembly (Liu and Cheng, 2009 with square root interpolation between 100 K spaced cross section libraries is used to model the Doppler broadening effect for fuel materials. This methodology has been verified to give reasonably accurate results (Chaudri et al, 2013).…”

Section: Monte Carlo N-particle (Mcnp) Transport Theory Codementioning

confidence: 99%

See 2 more Smart Citations

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Chaudri

Tian

et al. 2013

Progress in Nuclear Energy

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Section: Studied Fuel Assemblymentioning

confidence: 95%

Section: Studied Fuel Assemblymentioning

confidence: 99%

Section: Monte Carlo N-particle (Mcnp) Transport Theory Codementioning

confidence: 99%

See 1 more Smart Citation

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Chaudri

Tian

et al. 2013

Progress in Nuclear Energy

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“…According to the various conceptual SCWR designs [3][4][5], H-Power divided SCWR into two groups: one is the single-loop type and the other is the double-loop type. The validation of H-Power consists of two parts: for the singleloop SCWR, the data published by Jacopo [6] was used, while for the double-loop SCWR, the values of Qinshan Phase II [7] were used; though it is not the SCWR, we just use it for preliminary validation since the exact detail design data was rarely published.…”

Section: Introductionmentioning

confidence: 99%

Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor

Zhang

Sui

et al. 2014

Science and Technology of Nuclear Installations

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SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitoring and calibration of the SCWR. One visual software named H-Power was developed to calculate thermal power and its uncertainty of SCWR, in which the advanced IAPWS-IF97 industrial formulation was used to calculate the thermodynamic properties of water and steam. The ISO-5167-4: 2003 standard was incorporated in the code as the basis of orifice plate to compute the flow rate. New heat balance model and uncertainty estimate have also been included in the code. In order to validate H-Power, an assessment was carried out by using data published by US and Qinshan Phase II. The results showed that H-Power was able to estimate the thermal power of SCWR.

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“…In this paper, a threedimensional fuel model is established and applied to the thermal-hydraulic code. In COBRA-SC [31], the heat conduction equation Eq. (21) is discretized in axial, radial, and circumferential coordinates and solved simultaneously by the three-dimensional fuel model.…”

Section: A Correlation Of Circumferential Distribution Of Heat Transfmentioning

confidence: 99%

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

Yang

Liu

2017

Int J Energy Res

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SUMMARYIn the fuel assemblies in reactor core, the distribution of temperature is not uniform in the fuel rod along the circumferential direction. The circumferential temperature difference could be neglected for conventional assembly design but increases significantly in a tight lattice.To investigate the circumferential non-uniformity of heat transfer in rod bundles, this paper firstly establishes mathematical model and makes theoretical analyses, based on which influential non-dimensional numbers are summarized. Then, a semi-empirical correlation describing this phenomenon is proposed based on theoretical results and CFD sensitivity analyses. Finally, a three-dimensional model for cylindrical fuel is introduced in the thermal-hydraulic code to predict circumferential heat transfer non-uniformity in different geometry and flow conditions. To validate this model, some results are compared with experimental data of bundle test for subcritical and supercritical water.The three-dimensional fuel model for sub-channel code is a new numerical tool to predict the peak cladding and fuel temperature and can be applied in thermal-hydraulic analysis of fuel assemblies of tight lattice design.

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Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly

Cited by 47 publications

References 5 publications

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

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