KWU’s High Conversion Reactor Concept—An Economical Evolution of Modern Pressurized Water Reactor Technology Toward Improved Uranium Ore Utilization

Validation tests were made for the accuracy of cell calculation methods used in analyses of tight lattices of a mixed-oxide (MOX) fuel core in a high conversion light water reactor (HCLWR). A series of cell calculations was carried out for the lattices referred from an international HCLWR benchmark comparison, with emphasis placed on the resonance calculation methods; the NR, IR approximations, the collision probability method with ultra-fine energy group. Verification was also performed for the geometrical modelling; a hexagonal/cylindrical cell, and the boundary condition; mirror/white reflection. In the calculations, important reactor physics parameters, such as the neutron multiplication factor, the conversion ratio and the void coefficient, were evaluated using the above methods for various HCLWR lattices with different moderator to fuel volume ratios, fuel materials and fissile plutonium enrichments.The calculated results were compared with each other, and the accuracy and applicability of each method were clarified by comparison with continuous energy Monte Carlo calculations. It was verified that the accuracy of the IR approximation became worse when the neutron spectrum became harder. It was also concluded that the cylindrical cell model with the white boundary condition was not so suitable for MOX fuelled lattices, as for U0 2 fuelled lattices.

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Evaluation of DNBR under Operational and Accident Conditions for Double-Flat-Core Type HCLWR

Iwamura

Ōkubo

Murao

et al. 1991

Journal of Nuclear Science and Technology

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A double-flat-core type high conversion light water reactor (HCLWR) has been developed at JAERI to improve fuel utilization. Experimental and analytical studies on the departure from nucleate boiling ratio (DNBR) under operational and accident conditions for the HCLWR have been performed. It was found by comparing several critical heat flux (CHF) correlations with the CHF data obtained at JAERI and Bettis Atomic Power Laboratory that the KfK correlation has the most promising features for the application to the triangular tight lattice rod array. The minimum allowable DNBR (MDNBR) for the HCLWR was determined to be 1.28 by comparing the Bettis CHF data with the KfK correlation. The best-estimate code 1-TRAC was used for system transient calculations under the primary coolant pump trip and locked rotor accident conditions. The subchannel code COBRA-IV-I was then used to obtain local flow conditions and fuel rod surface heat flux. The analytical results indicated that an enough safety margin was assured under the steady-state operational condition. Under the accident conditions, the evaluated minimum DNBR's were also above the MDNBR criterion. Therefore, it was clarified that the present HCL WR design is feasible from a view point of the MDNBR criterion.

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KWU’s High Conversion Reactor Concept—An Economical Evolution of Modern Pressurized Water Reactor Technology Toward Improved Uranium Ore Utilization

Cited by 5 publications

References 2 publications

Control rod distribution for an HCPWR fuel assembly

Control rod distribution for an HCPWR fuel assembly

Accuracy of Cell Calculation Methods Used for Analysis of High Conversion Light Water Reactor Lattice

Evaluation of DNBR under Operational and Accident Conditions for Double-Flat-Core Type HCLWR

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