The benchmark employs many of the characteristics of the NEACRP L-335 Pressurised Water Reactor (PWR) benchmark proposed by Herbert Finnemann in 1991. The current problem adds the complexity of modelling a control rod ejection in a core loaded partially with weapons-grade MOX since the neutronic characteristics of plutonium are sufficiently different from uranium to significantly change the kinetics response of the reactor core. The reactor core chosen for the simulation was based on four-loop Westinghouse PWR power plant similar to the reactor proposed for plutonium disposition in the United States. It is relevant to current international plutonium use strategies as many of the commercial power plants in Europe and Japan already use MOX fuel. The United States was preparing to use MOX in light water reactors (LWRs) as part of its weapons plutonium disposition programme.
Data related to the MOX/UO2 Transient Benchmark can be requested from the NEA Data Bank: https://www.oecd-nea.org/tools/abstract/detail/NEA-1780/
This work has been performed under the auspices of OECD/NEA Working Party on Scientific Issues of Reactor Systems (WPRS) and is sponsored by US NRC and OECD/NEA.
The full benchmark information is available upon request from the OECD/NEA Data Bank on CD-ROM or DVD
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light water reactor (LWR) systems and processes in all stages of calculations. It is estimated through a simulation process of ten exercises in three phases provided by the benchmarking framework.
The main mission of the Working Group on Fuel Safety (WGFS) is to advance the current understanding and address cross-cutting issues related to fuel behaviour in accident conditions, including work on associated aspects of thermal-hydraulics, oxidation, chemistry, mechanical behaviour and reactor physics.
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.