Reactivity Insertion Accident Simulation of ELSY Lead Fast Reactor with RELAP5 Code
The Lead Fast Reactor (LFR) is considered one of the most promising advanced reactors able to fulfill the Gen-IV principles of sustainability, economic competitiveness, safety and proliferation resistance. The ELSY project (European Lead-cooled System), funded by the 6th European Framework Program, aimed at investigating the technical/economical feasibility of a high power critical fast reactor with waste transmutation capability. Among the innovative design solutions proposed, one of the most interesting reference option is the adoption of wrapper-less MOX fuel assemblies. To support the design phase, the thermal-hydraulic code RELAP5, modified to treat heavy liquid metals, has been employed for preliminary thermal-hydraulic and safety analysis with a conservative approach. In a following phase a detailed RELAP5 model of the reactor has been used to analyze several accident scenarios. The first part of the paper deals with the development of the thermal-hydraulic model and the elaborations carried out to simulate the neutronic feedback effects, taking advantage of the RELAP5 standard point-kinetic module. The results of simulations concerning protected and unprotected positive reactivity insertion accident (RIA) are discussed in the second part of the paper. They show that the core temperatures and the whole reactor conditions stay within the safety limits both in Design Basis Conditions (DBC) and in Design Extended Conditions (DEC). The simulations have been restricted to the beginning-of-cycle (BOC) conditions that resulted the most challenging from the safety point of view.
Lead Fast Reactor ELSY Project Thermal Hydraulics RELAP5 Reactivity InsertionAccident.
Massimiliano Polidori Giacomino Bandini Paride Meloni
ENEA Centro Ricerche Ezio Clementel Via Martiri di Monte Sole, 4, I-40129 Bologna
国际会议
上海
英文
620-631
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）