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KENO V. a validation of fuel pin experiments
| 题名： | KENO V. a validation of fuel pin experiments |
| 作者： | Westfall, R.M.;Dyer, H.R.; |
| 关键词： | 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CRITICALITY; CALCULATION METHODS; SPENT FUEL STORAGE; CROSS SECTIONS; FUEL PINS; K CODES; MONTE CARLO METHOD; PWR TYPE REACTORS; SIMULATION; SPENT FUEL ELEMENTS; VALIDATION; COMPUTER CODES; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; STORAGE; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS |
| 摘要： | This paper describes the results of computations performed on a set of critical experiments designed to simulate high-density storage of reactor fuel pins. The purpose of these computations is to validate the Monte Carlo criticality code KENO V.a with the four cross-section libraries provided with the SCALE modular code system. The principal conclusion drawn from this study is the satisfactory performance of the SCALE cross-section libraries in the analysis of systems containing consolidated light-water reactor fuel. As observed in previous studies, the ENDF/B-IV-based libraries undercalculate the effective neutron multiplication factor (k/sub eff/) by 1 to 2%k, depending on the degree of neutron moderation. 5 refs., 2 tabs. |
| 总页数： | Pages7 |
| 报告类型： | 科技报告 |
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