Conception of a full-core reactor model in transport theory

输运理论中全堆芯反应堆模型的概念

• 批准号: 107847-2006
• 负责人: Hébert, Alain
• 金额: $ 1.64万
• 依托单位: École Polytechnique de Montréal
• 依托单位国家: 加拿大
• 项目类别: Discovery Grants Program - Individual
• 财政年份: 2007
• 资助国家: 加拿大
• 起止时间: 2007-01-01 至 2008-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=364822
• 关键词: Conception; full; core; reactor; model

The future success on nuclear energy in Canada is closely related to the successful design of a third-generation reactor, permitting to lower the cost of electricity while increasing the safety margins. The ACR-1000, being designed by Atomic Energy of Canada Limited (AECL), is one such design. Later in time, fourth-generation reactors (Gen IV) are expected to produce very high temperature steam, a condition required for Hydrogen production. The AECL is proposing the Super Critical Water Reactor (SCWR) as a Gen IV concept. These reactors represent the most serious option to reduce both greenhouse effect and our dependency on fossil fuels. This NSERC/DG research proposal is related to the development of advanced numerical methods for setting reference reactor models for the ACR-1000 and for a high leakage core that could serve as a starting point for designing the SCWR. The advanced numerical methods being proposed in this application are solution techniques of the neutron transport equation with three common characteristics: (1) deterministic, (2) first-order transport operator and (3) superconvergent. Choosing deterministic approaches will enable us to implement them in the existing computer codes DRAGON V4 and TRIVAC (a subset of code DONJON V4). First order SN or Simplified PN approaches make possible the representation of voided (or close-to-void) regions and simplify the implementation of anisotropic scattering. Superconvergent approximations are those featuring primal-dual agreement, a numerical property that is related to an improvement of their accuracy for a given order of discretization. The following numerical approaches will be developed: (1) High-order diamond schemes and application to full-core problems (2) Development of 3D reactor models with the superconvergent SPN method (3) Development of the Slice Balance Approach and application to lattice and full-core problems.

加拿大核能未来的成功与第三代反应堆的成功设计密切相关，该反应堆可以降低电力成本，同时提高安全裕度。由加拿大原子能有限公司 (AECL) 设计的 ACR-1000 就是这样的设计之一。稍后，第四代反应堆（第四代）预计将产生非常高温的蒸汽，这是生产氢气所需的条件。 AECL 提议将超临界水反应堆 (SCWR) 作为第四代概念。这些反应堆是减少温室效应和我们对化石燃料依赖的最严肃的选择。该 NSERC/DG 研究提案涉及先进数值方法的开发，用于为 ACR-1000 和高泄漏堆芯设置参考反应堆模型，该模型可作为 SCWR 设计的起点。本申请中提出的先进数值方法是中子输运方程的求解技术，具有三个共同特征：（1）确定性，（2）一阶输运算子和（3）超收敛。选择确定性方法将使我们能够在现有计算机代码 DRAGON V4 和 TRIVAC（代码 DONJON V4 的子集）中实现它们。一阶 SN 或简化 PN 方法使空洞（或接近空洞）区域的表示成为可能，并简化了各向异性散射的实现。超收敛近似是具有原对偶一致性的近似，这是一种与给定离散阶数的精度提高相关的数值属性。将开发以下数值方法： (1) 高阶金刚石方案及其在全核问题中的应用 (2) 使用超收敛 SPN 方法开发 3D 反应堆模型 (3) 切片平衡方法的开发及其在晶格和全核问题中的应用。