1. NAME AND TITLE

SCOPE: Computer Code System for Shipping Cask Optimization and Parametric Evaluation.

2. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

3. CODING LANGUAGE AND COMPUTER

Fortran IV; IBM 3033.

4. NATURE OF PROBLEM SOLVED

Given the neutron and gamma-ray shielding requirements as input, SCOPE may be used as a conceptual design tool for the evaluation of various casks designed to carry square fuel assemblies, circular canisters of nuclear waste material, or circular canisters containing "intact" spent-fuel assemblies. It may be used to evaluate a specific design or to search for the maximum number of full assemblies (or canisters) that might be shipped in a given type of cask. In the "search" mode, SCOPE will use built-in packing arrangements and the tabulated shielding requirements input by the user to "design" a cask carrying one fuel assembly (or canister); it will then continue to increment the number of assemblies (or canisters) until one or more of the design limits can no longer be met. In each case (N = 1,2,3...), SCOPE will calculate the steady-state temperature distribution throughout the cask and perform a complete 1-D space/time transient thermal analysis following a postulated half-hour fire; then it will edit the characteristic dimensions of the cask (including fins, if required), the total weight of the loaded case, the steady-state temperature distribution at selected points, and the maximum transient temperature in key components. With SCOPE, the effects of various design changes may be evaluated quickly and inexpensively.

5. METHOD OF SOLUTION

SCOPE assumes that the user has already made an independent determination of the neutron and gamma-ray shielding requirements for the particular type of cask(s) under study. The amount of shielding required obviously depends on the type of spent fuel or nuclear waste material, its burnup and/or exposure, the decay time, and the number of assemblies or canisters in the cask. Source terms (and spectra) for spent PWR and BWR fuel assemblies are provided at each of 17 decay times, along with recommended neutron and gamma-ray shield thicknesses for Pb, Fe, and U-metal casks containing a number (1-25) of 1-, 2-, 3-, 4-, 7-, or 10-year-old PWR spent fuel assemblies.

6. RESTRICTIONS OR LIMITATIONS

The key physical features of those casks considered by the SCOPE code include: an inner steel shell, a gamma-ray shield, an outer steel shell, a neutron shield, and an outside barrel. Depending on the amount of decay heat that must be dissipated, the cask(s) may or may not have circumferential fins. Inside the cask(s), the spent fuel assemblies (or canisters) may be separated by means of an aluminum or copper insert. It is assumed that the spent fuel is to be shipped dry (i.e., casks with forced circulation cooling systems are not considered). Lead, iron, or uranium metal may be specified as the gamma-ray shielding material, while the neutron shield is always assumed to be a common mixture of water and ethylene glycol containing ~1 wt% boron.

7. TYPICAL RUNNING TIME

On an IBM 3033/MVS machine, SCOPE requires ~0.13 seconds of CPU time for each cask analyzed.

8. COMPUTER HARDWARE REQUIREMENTS

This version of SCOPE is operable on an IBM 3033 computer with a minimum of 105 K bytes of storage.

9. COMPUTER SOFTWARE REQUIREMENTS

The IBM version runs on the IBM 3033 OS/MVS or IBM 360/91 OS/MVT systems with standard I/O. The code will compile under either the Fortran H or Fortran Q compiler.

10. REFERENCE

J. A. Bucholz, "Scoping Design Analyses for Optimized Shipping Casks Containing 1-, 2-, 3-, 5-, 7-, or 10-Year-Old PWR Spent Fuel," ORNL/CSD/TM-149 (January 1983).

Background information:

"SCALE: A Modular Code System for Performing Standardized Analyses for Licensing Evaluation," NUREG/CR-0200 (ORNL/NUREG/CSD-2), Vols. I, II, and III (April 1982).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source code plus sample problem input and output.

12. DATE OF ABSTRACT

March 1985, revised October 1991.