This study was conducted to assess a kind of specific cement (ASC) extensively and recommend a suitable formula for the immobilization of the radioactive ion exchange resins from China Institute of Atomic Energy (CIAE). A mixture response surface approach was employed to design the experiment and interpret the results. Compared with the blend composed of ordinary Portland cement (OPC), an optimum combination, resin: .17 (dry wt/wt); ASC: .43; zeolite: .10, and water: .30, was determined within a series of restrictions for such properties as the slump, the 28-d compressive strength, the water immersion, the thaw-freeze resistance, the irradiation resistance, and the leaching rate. The diffusivities of 137 Cs and 60 Co of the waste forms resulting from the formula were 2.72E-06 (cm 2 /d) and 1.63E-07 (cm 2 /d) after 123 d, respectively. The loading amount of spent resins in the ASC form was larger than that in the OPC form by 5% under the equal performance indexes. The microanalysis indicated that there were many interlaced columnlike crystals (ettringites) developed in ASC-resin concrete. This structure could enhance the strength and stabilization of the waste forms significantly.