THE CHEMISTRY OF FUEL-REPROCESSING - PRESENT PRACTICES, FUTURE-TRENDS

被引:18
作者
CAMPBELL, DO [1 ]
BURCH, WD [1 ]
机构
[1] OAK RIDGE NATL LAB,DIV FUEL RECYCLE,OAK RIDGE,TN 37831
来源
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY-ARTICLES | 1990年 / 142卷 / 01期
关键词
D O I
10.1007/BF02039470
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The chemistry of reprocessing, the recovery and purification of plutonium from uranium and fission products produced in the fuel of a nuclear reactor, was surveyed and is described. Reprocessing presented unique chemical problems because of the intense radioactivity, the extreme degree of separation required, and the diversity of elements present. These challenges were met, and improved processes have evolved with time. After 50 years, improvements are still being introduced into the classical solvent extraction processes. In the future, integration of process steps across the entire fuel cycle and increased attention to waste management and environmental considerations are anticipated. © 1990 Akadémiai Kiadó.
引用
收藏
页码:303 / 320
页数:18
相关论文
共 36 条
  • [1] BARNEY GS, 1976, J INORG NUCL CHEM, V38, P1677
  • [2] BENKER DE, 1986, ENC86 T, P109
  • [3] RATE OF REACTION OF NITROUS ACID WITH HYDRAZINE AND WITH SULPHAMIC ACID - ITS APPLICATION TO NITROUS ACID CONTROL IN 2-PHASE INDUSTRIAL SYSTEMS
    BIDDLE, P
    MILES, JH
    [J]. JOURNAL OF INORGANIC & NUCLEAR CHEMISTRY, 1968, 30 (05): : 1291 - &
  • [4] BOUDRY JC, 1974, P INT SOLVENT EXTRAC, V1
  • [5] BOYD GE, 1970, P NUCL ENERGY 3, V4, P319
  • [6] BRONW PGM, 1961, PROG NUCL ENERGY 3, V2, P129
  • [7] BURROS L, 1986, CHEM PROG, P35
  • [8] CAMPBELL DO, 1986, P INT SOLVENT EXTRAC, V1, P301
  • [9] CAMPBELL WM, 1956, NUCLEONICS, V14, P92
  • [10] Cleveland J. M., 1970, CHEM PLUTONIUM