Download Intro_RXSP Introduction The accuracy of the nuclear cross section data is a prerequisite for the accuracy of reactor neutron transport calculations, i.e. MC method. RXSP is a nuclear Cross Section Processing code being originally developed by REAL group, Department of Engineering Physics, Tsinghua University, which is mainly intended to reactor analysis. The current version is RXSP-Beta 2.0 released in August,2013 domestically in China Mainland. The Beta3.0 version is being developed jointly by UNIST and Tsinghua University(per the agreement of Prof. Lee and Prof. WANG). Modules and Functions Functional Modules Features
Validation Cross Sections Library Processing Validation of Criticality Benchmark Suites Total view of differences of k-effective of 132 benchmarks Neutron Spectrum of four cases: Case 1: heu-met-fast-001-case-a Case 2: ieu-met-fast-002 Case 3 : leu-sol-therm-007-case-14 Case 4 : pu-met-fast-001 Simulation time Extension
Flow chart of uncertainty quantification |
4. Code Development >