在Na-Ca-Cl溶液中，MX-80、伊利石、页岩和石灰岩对U（IV）的吸附

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2025-05-28 DOI:10.1016/j.net.2025.103720

Shinya Nagasaki , Zhiwei Zheng , Jianan Liu , Jieci Yang , Tianxiao Tammy Yang

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引用次数: 0

摘要

铀已被确定为对乏核燃料深地质储存库（DGR）进行安全评估的一个重要因素。在还原条件下，在ph = 4-10 （MX-80、伊利石、页岩）和pHm = 5-10（石灰岩）条件下，离子强度为0.1-6 mol/kgw (m)的Na-Ca-Cl溶液中，研究了四价U（IV）在MX-80膨润土、伊利石、页岩和石灰岩上的吸附。MX-80对U（IV）的吸附随着pHm的增大而增大，直至pHm = 8，达到一个吸附平台。从pHm = 4到pHm = 5，伊利石和页岩对U（IV）的吸附逐渐增加，并达到一个吸附平台。石灰石对U（IV）的吸附在pHm≤7时随pHm的增大而增大，随后随pHm的增大而急剧减小。四种固体对U（IV）的吸附不受Na-Ca-Cl溶液离子强度的影响。采用2位质子解非静电表面络合和阳离子交换（2SPNE SC/CE）模型，通过3个内球表面络合反应，成功地模拟了在Na-Ca-Cl溶液中，x -80和伊利石对U（IV）的吸附。优化了表面络合常数（log K0）的取值。

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Sorption of U(IV) on MX-80, illite, shale and limestone in Na-Ca-Cl solutions

Uranium has been identified as an element of interest for the safety assessment of a deep geological repository (DGR) for used nuclear fuel. This paper studied the sorption of tetravalent U(IV) onto MX-80 bentonite, illite, shale and limestone in ionic strength 0.1–6 mol/kgw (m) Na-Ca-Cl solutions at pH_m = 4–10 (for MX-80, illite, shale) and pH_m = 5–10 (for limestone) under reducing conditions. Sorption of U(IV) on MX-80 increased with pH_m until pH_m = 8 and then reached a sorption plateau. Sorption of U(IV) on illite and shale increased from pH_m = 4 to 5 and then reached a sorption plateau. Sorption of U(IV) on limestone increased with pH_m up to pH_m = 7 and then steeply decreased with pH_m. Sorption of U(IV) on all four solids was not influenced by the ionic strength of Na-Ca-Cl solutions. The sorption of U(IV) onto MX-80 and illite in Na-Ca-Cl solutions was successfully simulated by a 2 site protolysis non-electrostatic surface complexation and cation exchange (2SPNE SC/CE) model using three inner-sphere surface complexation reactions. Values of surface complexation constants (log K⁰) were optimized.

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来源期刊

Nuclear Engineering and Technology 工程技术-核科学技术

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development