Establish fuel reliability in CANDU

燃料的安全性和性能一直是核能事业的重要课题。该提案旨在证明CANDU燃料在正常运行条件下（NOC）的可靠性，以及在冷却剂损失事故（LOCA）条件下的乏燃料安全裕度。为了满足日益增长的能源需求，以及提高电厂和核心设计效率以保持与其他能源的竞争力，核能公用事业公司采取了措施来满足这些需求。项目一是通过实现“零燃料缺陷”来支持运行。将开发一种强有力的方法，使用基于统计的方法，以高度准确地评估目前CANDU燃料设计和操作中存在的安全边际。实际的燃料制造和运行数据将用于预测NOC期间燃料失效的概率。将使用与电力公司的加油指导方针密切一致的加油方法（WIMS/RFSP）创建一套通用的运行数据。COMSOL Multiphysics®燃料性能代码（FAST）是由RMC开发并根据行业标准代码进行验证的，将用于预测燃料故障。2011年福岛第一核电站（Fukushima Daiichi）发生严重断电事故后，乏燃料池的储存已成为国际关注的焦点。项目2将确认CANDU乏燃料池中的LOCA在干干后进展足够缓慢，可以确保操作人员进行干预，从而排除失控氧化和锆火灾的可能性。拟议中的项目将满足经合组织在2015年报告中概述的对CANDU严重事故建模工具的需求。由加拿大核实验室、加拿大核安全委员会和经合组织核能机构编制的现象排名表将用于支持模型的开发。

Fuel safety and performance are always important topics to nuclear utilities. This proposal is to demonstrate CANDU fuel reliability under Normal Operating Conditions (NOC), and spent fuel safety margin under Loss of Coolant Accident (LOCA) Conditions. To meet an increasing demand for energy, as well as improve plant and core design efficiencies to remain competitive with other energy sources, nuclear utilities took measures to meet these needs. Project#1 is to support operation by achieving "zero fuel defects". A robust methodology, using a statistical based approach, to assess the safety margin present in the current design and operation of CANDU fuels with a high degree of accuracy will be developed. The actual fuel manufacturing and operating data will be used to predict the probability of fuel failure during NOC. A generic set of operating data will be created using refuelling methodologies (WIMS/RFSP) that coincide closely with the fuelling guidelines from power utilities. A COMSOL Multiphysics® fuel performance code (FAST), which was developed at RMC and validated against industry standard codes, will be used to predict fuel failure. Spent fuel pool storage has become a focus of international concerns after the severe loss of power accident in 2011 at the Fukushima Daiichi power plants. Project #2 will confirm a LOCA in a CANDU spent fuel pool has sufficiently slow post-dryout progression that operator intervention can be assured and, hence, to preclude the possibility of runaway oxidation and zirconium fires. The proposed project will address the need for a CANDU severe accident modelling tool as outlined by the OECD in their 2015 report. Phenomena ranking tables developed by the Canadian Nuclear Laboratories, the Canadian Nuclear Safety Commission, and the OECD-Nuclear Energy Agency will be used to support the model development.