[en] Previous analyses have examined a limited number of the alternatives available for designing an LMFBR spent-fuel shipping cask (SFSC) using a non-volatile neutron shield; i.e., a neutron shield which will not be lost in an accident involving a fire. The present study extends the scope of these hypothetical designs to include combinations of volatile and non-volatile neutron shield materials

[en] Predictions of the composition of high-level waste from U-fueled LWRs have been used to calculate the neutron and gamma-ray sources in such waste at cooling times of 3 and 10 years. The results are intended for interim application to studies of waste shipping and storage pending the availability of more exact knowledge of fuel recycling and of waste concentration and solidification

[en] This report presents estimates of certain transportation costs, in 1979 dollars, associated with Light-Water Reactor (LWR) once-through and recycle fuel cycles. Shipment of fuel, high-level waste and low-level waste was considered. Costs were estimated for existing or planned transportation systems and for recommended alternate systems, based on the assumption of mature fuel cycles. The annual radioactive material transportation costs required to support a nominal 1000-MW(e) LWR in a once-through cycle in which spent fuel is shipped to terminal storage or disposal were found to be approx. $490,000. Analogous costs for an average reactor operating in a fuel cycle with uranium and plutonim recycle were determined to be approx. $770,000. These results assume that certain recommended design changes will occur in radioactive material shipping systems as a mature fuel cycle evolves

[en] The use of adjoint techniques to determine the interaction of externally incident collimated beams of particles with cylindrical targets is a convenient means of examining a class of problems important in radiation transport studies. The theory relevant to such applications is derived, and a simple example involving a fissioning target is discussed. Results from both discrete ordinates and Monte Carlo transport-code calculations are presented, and comparisons are made with results obtained from forward calculations. The accuracy of the discrete ordinates adjoint results depends on the order of angular quadrature used in the calculation. Reasonable accuracy by using EQN quadratures can be expected from order S₁₆ or higher

[en] Neutron and gamma-ray transport calculations in one-dimensional cylindrical geometry have been performed on a trial reference LMFBR spent-fuel shipping cask that could transport one CRBR subassembly. In the study it was assumed that a layer of depleted U and a layer of neutron shielding materials were sandwiched between 5.08-cm-thick (2-in.) layers of stainless steel. The thicknesses of the internal layers were adjusted until a balanced dose rate (50 percent neuton and 50 percent gamma-ray) of 5 mrem/hr was achieved at a point 1.83 m (6 ft) from the cask surface. Neutron-shield materials considered were LiH, Be, B₄C, DiH₂.₅, and C (graphite). Of these materials, LiH provided the smallest, lightest, and least expensive cask; however, its use would be contigent on expansion of production facilities for LiH and development of a canning or cladding procedure. The B₄C shielded cask would offer the best alternative if the designs were limited to those using currently available materials

[en] Three-dimensional Monte Carlo criticality calculations have been performed with KENO IV on two types of LMFBR subassemblies placed in configurations considered appropriate for shipping-cask applications. The report presents the effects of geometry, coolant, and loading changes--along with shield/structure material selection--on the self-multiplication of such systems. An example is shown which permits the determination of the maximum payload of CRBR fuel allowed under specified limits for k/sub eff/. Fuel enrichment, number of subassemblies, and type of coolant used are generally the most sensitive variables affecting self-multiplication. Of lesser importance are the type of gamma shield used and the pitch between subassemblies; the choice of neutron-shield material and outer case structure are of least importance. The correlations presented are expected to be useful in making decisions related to shipping-cask designs

[en] Design alternatives for the International Atomic Energy Agency's Spent Fuel Attribute Tester (SFAT) were evaluated using radiation transport calculations. Several design changes were recommended and implemented in a new SFAT device. The new SFAT was tested on September 8 and 9, 1993, at the Industrial Power Company, Ltd. intermediate spent fuel storage facility in Olkiluoto, Finland. The new SFAT performed very well. The results of the tests are compared with predictions made during the SFAT optimization study

[en] The purpose of this report is to describe a method, developed at Sandia National Laboratories, for calculating volumetric, unshielded, gamma radiation source spectra with arbitrary energy group structures from essentially arbitrary mixtures of actinide isotopes. The computer code and data base are combined as INRAD. These spectra can be used to describe the source for gamma radiation transport codes. Coupled with this source routine is a special version of the one-dimensional, discrete ordinates, radiation transport code XSDRN that uses the spectrum generating routine to define sources in an appropriate energy group structure. 15 refs., 34 figs., 10 tabs

[en] Remote monitoring systems presently operating in facilities in a number of countries around the world are providing valuable information on the installation and operation of such systems. Results indicate they are performing reliably. While the technology for remote monitoring exists today, it may be some time before numerous constraints on implementation can be resolved. However, the constraints should not prevent the designing of systems that can be used for remote monitoring. Selection of the proper technology path for future development should include a flexible approach to front-end detection, data formats, data processing, and other areas. A brief description of two of the existing remote monitoring systems, and some general recommendations for future remote monitoring systems, will be presented

No abstract available