Knowledge Resource Center for Ecological Environment in Arid Area
| DOI | 10.2172/140363 |
| 报告编号 | PNL--8659 |
| 来源ID | OSTI_ID: 140363 |
| AREST model description | |
| Engel, D.W.; McGrail, B.P. | |
| 英文摘要 | The Office of Civilian Radioactive Waste Management and the Power Reactor and Nuclear Fuel Development Corporation of Japan (PNC) have supported the development of the Analytical Repository Source-Term (AREST) at Pacific Northwest Laboratory. AREST is a computer model developed to evaluate radionuclide release from an underground geologic repository. The AREST code can be used to calculate/estimate the amount and rate of each radionuclide that is released from the engineered barrier system (EBS) of the repository. The EBS is the man-made or disrupted area of the repository. AREST was designed as a system-level models to simulate the behavior of the total repository by combining process-level models for the release from an individual waste package or container. AREST contains primarily analytical models for calculating the release/transport of radionuclides to the lost rock that surrounds each waste package. Analytical models were used because of the small computational overhead that allows all the input parameters to be derived from a statistical distribution. Recently, a one-dimensional numerical model was also incorporated into AREST, to allow for more detailed modeling of the transport process with arbitrary length decay chains. The next step in modeling the EBS, is to develop a model that couples the probabilistic capabilities of AREST with a more detailed process model. This model will need to look at the reactive coupling of the processes that are involved with the release process. Such coupling would include: (1) the dissolution of the waste form, (2) the geochemical modeling of the groundwater, (3) the corrosion of the container overpacking, and (4) the backfill material, just to name a few. Several of these coupled processes are already incorporated in the current version of AREST. |
| 出版年 | 1993 |
| 报告类型 | Technical Report |
| 语种 | 英语 |
| 国家 | 美国 |
| 来源学科分类 | 05 NUCLEAR FUELS ; RADIOACTIVE WASTE FACILITIES ; RADIONUCLIDE MIGRATION ; COMPUTERIZED SIMULATION ; UNDERGROUND STORAGE ; RADIOACTIVE WASTE STORAGE ; WASTE FORMS ; DECAY ; DISSOLUTION ; GROUND WATER ; GEOCHEMISTRY ; CORROSION ; BACKFILLING ; Yucca Mountain Project |
| URL | http://www.osti.gov/scitech/servlets/purl/140363 |
| 资源类型 | 科技报告 |
| 条目标识符 | http://119.78.100.177/qdio/handle/2XILL650/265383 |
| 推荐引用方式 GB/T 7714 | Engel, D.W.,McGrail, B.P.. AREST model description,1993. |
| 条目包含的文件 | 条目无相关文件。 | |||||
| 个性服务 |
| 推荐该条目 |
| 保存到收藏夹 |
| 导出为Endnote文件 |
| 谷歌学术 |
| 谷歌学术中相似的文章 |
| [Engel, D.W.]的文章 |
| [McGrail, B.P.]的文章 |
| 百度学术 |
| 百度学术中相似的文章 |
| [Engel, D.W.]的文章 |
| [McGrail, B.P.]的文章 |
| 必应学术 |
| 必应学术中相似的文章 |
| [Engel, D.W.]的文章 |
| [McGrail, B.P.]的文章 |
| 相关权益政策 |
| 暂无数据 |
| 收藏/分享 |
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。
