MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING

Abramczyk, G ; Paul Blanton, P ; Kurt Eberl, K

Savannah River Site (S.C.)

关键词: Criticality;    Testing;    Safety Analysis;    42 Engineering;    Packaging;   

DOI  :  10.2172/891524
RP-ID  :  S-SARP-G-00001 REV 0
RP-ID  :  DE-AC09-96SR18500
RP-ID  :  891524

美国|英语

来源: UNT Digital Library

【 摘 要 】

This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.