抄録
Standard code for concrete reactor vessles and containments is proposed and issued by A. C. I committee 359, ASME subcomittee on nuclear power. This standard code is called "ASME. Section III. Division 2." We have not only studied of the design shear stresses and these general ideas, but checked adaptability for Japanese design condisions. Many quetions and points at issue is discussed theoretically. And more suitable criteria of design shear strength for our country is proposed.
