This report was prepared a* an account of work sponsored by an agency of the U mted States Government Neither the U nited States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or issponsibiiity for the accuracy, completeness, or usefulness of sny information, apparatus, product, or process dacl>sed. or represents that it* use would not mf nn-^e privately owned rights Reference herein to any specific commercial product, process, or service by trade name, trademark. manufacturer or otherwise, does not necessarily constitute or imply its endorsement recommendation, or favoring by the >jnrt«*i States Government or eny agency thereof The views and opinions of author* expressed herein do not necessarily ttate or reflect those of the United States Government or any agency thereof i DISCLAIMER This report was prepared as an acconnt o>' work spuosoied by ar agency of the United States Government. Neither the United States Government nor aay agcacy thereof, oor any of their employees, make* aay warranty, express or implied, or assamet aay legal liability or responsi bility for the accuracy, comptetcrcss. or asefalacss of any information, apparauu. product, or process disttand. or ret reseats that its ase woald not iafriage privately owned rights. Refer ence hcretn to aay specific commercial prodwet, process, or scrvics by traie name, trademark, maaafactBrer. or otherwise dees aot necessarily comitate or imply its endorsement, recommeadatioa. or favoring by the United Slates Government or any agency thereof. The views and opjaiean of aatbors expressed beret* do not necessarily state or reflect those of the United States Government or aay agcacy thereof. rtr\»»» * ** _ --vjruxut V,£>U/TM 244 DE88 003658

No abstract

Experimental data on isotopic concentrations in irradiated nuclear fuel are essential for the validation of computational methods and nuclear data applied in the reactor modeling and simulations used in spent fuel safety and nuclear safeguards. This study investigates the potential use of recently declassified experimental data from the Hanford B reactor as a reactor and spent fuel benchmark. The experiments, performed in 1967, were the first in a series of carefully-designed tests to measure fuel performance and production capabilities at different locations in the reactor and for different exposures. Unlike most spent fuel benchmarks involving commercial fuel, the Hanford B data include unique measurements for very low exposure production fuel, with burnups less than 2,900 MWd/MTU. This report provides an assessment of the measurement data, uncertainties, design data, and operating history documentation, and describes preliminary benchmark models and simulation results. Areas where additional information would improve the quality of the benchmark are identified, as are potentially significant deficiencies in currently available nuclear cross-section data for simulating low-exposure irradiations.

No abstract

No abstract