Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Foamglas Shipping Container

Abstract

An analytical evaluation of the Oak Ridge National laboratory lORM.) Foamg!a> Shipping Container was made to demonstrate its compliance with the regulations c ;>vcining offsite radioactive material shipping packages. The evaluation encompass "d five primary categories: structural integrity, thermal resistance, radiation >h:c!din«. nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicat lc regulations. I. INTRODUCTION When a puv" r >gc is to be used in offsitc shipments of radioactive or fissile material, it is subject to regular-ins governing its structural integrity, heat dissipation capabilities, shielding ability, nuclear cn.icality safety, and quality assurance. The safety standards for the packaging of radioactive and fissile materials arc set forth in Chapter 0529 of the I nitcd States Dcpa ment of Energy (DOE) Manual. 1 To secure approval for shipment, it must be shown by test, by experimental data, or by computational methods that the package complies with these regulations. Th'.-Oak Ridge National Laboratory (ORNL) Foamglas Shipping Container was evaluated both r.y test and analyses and shown to meet all applicable regulations. The methods used md the rrvjlt* of the evaluation are reported here. The ORNL F fttnglas Shipping Container is illustrated in Fig. I.I. Seventy-two containers have been fabricated from dra»vings i} and identified by the applicable Department of Transportation ."OOT) Special Permit No. 5795 (Appendix 9.1); most remain in sen ice (sec Sect. 6). An !n;erim Certificate of Compliance has been issued (Appendix 9.2). and the containers have been properly identified. This SARP. when approved, will complete the Nuclear Rcgoiauov Commission (NRC) requirements, and a permanent certificate of compliance *r-V issued. The container is used to ship uranium and plutonium isotopes cither singly or in mixture as metal or oxide. Shipments employing polyethylene bottles will be limited to 5 W Kfj output. Other shipment; will be limited to 10 W. As shown in : ig. LI. the radioactive material in its container is placed inside the flanged ami gaskctcd starless steel inner chamber that is centered in a 55-gal drum. The space between thinner ch.iirbt and the drum is filled with Foamglas. (Sec Sect. I.I for composition of FYumglas.? 0«NL Dtt« M-I4M2 A6 *V/lTH LOCK NUT Fig. 1.1 Foamglas Shipping Container. 3 I.I Description of Foamglas Shipping Container The pan numbers listed in this text refer to encircled numbers in Fig. 1.2. The external part of the Foamglas Shipping Container (Fig. 1.2) is a carbon steel drum. 23.0 in. OD by 35-1 16-in. long (part 10). which is identified as a Specification PH package (Sect. 2.1). Suspended inside the drum is a flanged and gasketed stainless steel inner container which meets specification 2R (Sect. 2.2) and has inside dimensions of 4.81 in. diam by IX in. long. The side wall of the inner container is made trom a 5-in.-diam sched-80 pipe (part II) which has a 0.375-in. wall. The bottom of the in...

Safety Analysis Report for Packaging (SARP): Model AL-M1 nuclear packaging (DOE C of C No. USA/9507/BLF)

“…In the free drop container of 18-gauge wall thickness were tested [19,20,21]. test, the edge striking the surface was deformed, the ring clamp was dented, but the package remained intact.…”

Safety Analysis Report for Packaging (SARP): Models AL-M3 and AL-M6 nuclear packaging (DOE C of C No. USA/5790/BLF and No. USA/5791/BLF)

“…At the Oak Ridge National Laboratory, three packages based on a 55-gal DOT 17H container of 18-gauge wall thickess were tested [22,23,24]. In the free drop test, the edge striking the surface was deformed, the ring clamp was dented, but the package remained intact.…”