原文传递
Benchmark data for validating irradiated fuel compositions used in criticality calculations
| 题名： | Benchmark data for validating irradiated fuel compositions used in criticality calculations |
| 作者： | Talbert, R.J.;Bierman, S.R.; |
| 关键词： | 42 ENGINEERING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUELS; TRANSPORT; SPENT FUEL STORAGE; RADIOCHEMICAL ANALYSIS; CRITICALITY; SAFETY; BENCHMARKS; COMPUTER CODES; REACTIVITY |
| 摘要： | To establish criticality safety margins utilizing burnup credit in the storage and transport of spent reactor fuels requires a knowledge of the uncertainty in the calculated fuel composition used in making the reactivity assessment. To provide data for validating such calculated burnup fuel compositions, radiochemical assays have been obtained as part of the United States Department of Energy From-Reactor Cask Development Program. Assay results and associated operating histories on the initial three samples analyzed in this effort are presented. The three samples were taken from different axial regions of a Pressurized Water Reactor fuel rod and represent radiation exposures of about 37, 27, and 44 GWd/MTU. The data are presented in a benchmark type format to facilitate identification/referencing and computer code input. |
| 总页数： | 71p |
| 报告类型： | 科技报告 |
相关文献
- Evaluation of measured LWR spent fuel composition data for use in code validation
- Computational Physics and Engineering Division Bounding Criticality Safety Analyses for Shipments of Unconfigured Spent Nuclear Fuel
- Bounding criticality safety analyses for shipments of unconfigured spent nuclear fuel
- Packaging design criteria for the MCO cask
- Feasibility of subcriticality and NDA measurements for spent fuel by frequency analysis techniques with{sup 252}Cf
- Criticality Safety Scoping Study for the Transport of Weapons-Grade Mixed-Oxide Fuel Using the MO-1 Shipping Package
检索历史
应用推荐
