PROCESSING OF REACTOR-PRODUCED W-188 FOR FABRICATION OF CLINICAL-SCALE ALUMINA-BASED W-188/RE-188 GENERATORS

被引:104
作者
KNAPP, FF
CALLAHAN, AP
BEETS, AL
MIRZADEH, S
HSIEH, BT
机构
[1] Nuclear Medicine Group, Health Sciences Research Division, Oak Ridge National Laboratory (ORNL), Oak Ridge, TN 37830-6229
关键词
D O I
10.1016/0969-8043(94)90026-4
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
The traditional technique for processing of reactor-irradiated W-186-enriched tungsten oxide (WO3) targets involves formation of W-188-sodium tungstate solutions by target dissolution in 0.1 M NaOH. Following long irradiations (>21 days) in the ORNL High Flux Isotope Reactor (HFIR) the (WO3)-W-186 targets contain a NaOH-insoluble W-188-labeled black solid (approx. 30-50% of total activity) which decreases the yield and specific activity of the processed W-188 (e.g. 5-6 mCi/mg W-186 for a 79-day irradiation). The black material is postulated to represent a ''tungsten blue'' insoluble polymeric form of tungsten oxide, which we have now found to dissolve in 0.1 M NaOH containing 5% sodium hypochlorite solution. Complete dissolution results in a significant increase in the yield and specific activity of sodium W-188-tungstate. As an alternative approach, irradiated W-186-enriched metal targets dissolve in sodium hydroxide solution by cautious addition of <30% hydrogen peroxide. Sodium W-188-tungstate solutions prepared from processing of such metal targets show no evidence of residual black insoluble material. Specific activity values for completely dissolved HFIR-irradiated W-186 targets have increased to 10 mCi/mg (43.5 days) and 12.9 mCi/mg (49.2 days). Large clinical scale (>1 Ci) generators prepared from hypochlorite-processed W-186 oxide or peroxide-processed W-186 metal targets exhibit the expected Re-188 high yield and low W-188 breakthrough.
引用
收藏
页码:1123 / 1128
页数:6
相关论文
共 24 条
  • [1] Callahan A.P., 1992, RADIOACT RADIOCHEM, V3, P46
  • [2] CALLAHAN AP, 1992, APPL RADIAT ISOTOPES, V43, P801
  • [3] CALLAHAN AP, 1989, NUC COMPACT, V20, P3
  • [4] COTTON FA, 1973, ADV INORGANIC CHEM
  • [5] EHRHARDT G J, 1987, Journal of Nuclear Medicine, V28, P656
  • [6] EHRHARDT GJ, 1993, J NUCL MED, V34, pP38
  • [7] EHRHARDT GJ, 1992, RADIOACT RADIOCHEM, V3, P38
  • [8] EHRHARDT GJ, 1990, TECHNETIUM RHENIUM C, V3, P631
  • [9] EHRHARDT GJ, 1992, 1992 U MISS RES REAC
  • [10] GANIEV SU, 1973, RUSS J INORG CHEM, V18, P370