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Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER 4/017 Pages: 8 Published: Jan 2001
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View License Agreement Source: STP1398-EB Abstract A review of the results obtained in the framework of the Project is presented in the paper. The database consists of experimental data obtained in a model of WWER-1000 assembled in the LR-0 experimental reactor in NRI. The differential neutron spectra measurements were carried out over the water layer between the barrel simulator and reactor pressure vessel (RPV) simulator and over the RPV simulator thickness. The core power distribution was measured by means of gamma scanning of fuel elements (several hundreds of elements for the radial distribution and several tens for the axial one). The core power distribution calculations were done by MOBY DICK (2D several groups, diffusion code) and the Monte Carlo Code MCU—RFFI/A, the transport calculations were performed with deterministic codes in laboratories of the participating countries. The neutron spectra were compared in BUGLE 96 format. Keywords: reactor pressure vessel benchmark, neutron spectrometry Paper ID: STP13611S Committee/Subcommittee: E10.08 DOI: 10.1520/STP13611S ASTM International is a member of CrossRef. | ||