Spatial Kinetics Calculations of MOX Fueled Core: Variant 22

Pavlovichev, A.M.

Oak Ridge National Laboratory

关键词: Mixed Oxide Fuels;    Plutonium Recycle;    Reactor Kinetics;    Wwer Type Reactors;    Steam Lines;   

DOI  :  10.2172/777640
RP-ID  :  ORNL/SUB/99-B99398V-6
RP-ID  :  AC05-96OR22464
RP-ID  :  777640

美国|英语

来源: UNT Digital Library

【 摘 要 】

This work is part of a Joint US/Russian Project with Weapons-Grade Plutonium Disposition in VVER Reactors and presents the results of spatial kinetics calculational benchmarks. The examinations were carried out with the following purposes: to verify one of spatial neutronic kinetics model elaborated in KI, to understand sensibility of the model to neutronics difference of UOX and MOX cores, to compare in future point and spatial kinetics models (on the base of a set of selected accidents) in view of eventual creation of RELAP option with 3D kinetics. The document contains input data and results of model operation of three emergency dynamic processes in the VVER-1000 core: central control rod ejection by pressure drop caused by destroying of the moving mechanism cover; overcooling of the reactor core caused by steam line rupture and non-closure of steam generator stop valve; and the boron dilution of coolant in part of the VVER-1000 core caused by penetration of the distillate slug into the core at start up of non-working loop.