Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (2): 20601-020601.doi: 10.11889/j.0253-3219.2020.hjs.43.020601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Development and validation of AHD1.0 based on ENDF/B-VII.1

Haibo TANG1,2,Binhang ZHANG1,2(),Xianbao YUAN1,2,Yonghong ZHANG1,2   

  1. 1. College of Mechanical & Power Engineering, China Three Gorges University, Yichang 443002, China
    2. Hubei Key Laboratory of Hydroelectric Machinery Design & Maintenance, China Three Gorges University, Yichang 443002, China
  • Received:2019-09-30 Revised:2019-12-06 Online:2020-02-15 Published:2020-02-24
  • Contact: Binhang ZHANG E-mail:evanustc@mail.ustc.edu.cn
  • About author:TANG Haibo, male, born in 1987, graduated from North China Electric Power University with a master’s degree in 2013, focusing on reactor physics research
  • Supported by:
    National Natural Science Foundation of China(11805112)

Abstract: Background

Nuclear database is the basis of neutron transport calculation. It provides necessary nuclear data for lattice program. At present, the nuclear data of MCNP program are developed based on ENDF/B-VII.0 library or evaluation library of previous version. The latest version of ENDF/B series libraries was released in 2011. The incident neutron library contains 423 nuclides, 32 new nuclides and 2 natural nuclides are reduced. A total of 234 materials have been updated on the basis of ENDF/B-VII.0.

Purpose

This study aims to produce Advanced hybrid database (AHD) 1.0 for MCNP program.

Methods

Based on the ENDF/B-VII.1 evaluation library, the NJOY was used to produce the AHD1.0 for MCNP. The highly enriched uranium, the medium enriched uranium and low enriched uranium with fast spectra, intermediate spectra and thermal spectra benchmarks were selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) to validate the this library. The results of MCNP were compared with the experiments.

Results

The calculation results coincide well with the experimental values, but when elements such as W, Fe, Gd are contained, the uncertainty range of the benchmark is excedded due to unavailable data in the library or the source of the evaluation library for the nuclide.

Conclusions

The results show that the AHD1.0 is reliable, can be used in nuclear design.

Key words: AHD1.0, ENDF/B-VII.1, NJOY, AHD1.0 library, Critical benchmark validation

CLC Number: 

  • Tl329.3