Analysis of High Enriched Uranyl Nitrate Solution Containing Cadmium
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
A benchmark evaluation has been performed for a set of twenty-one critical experiments involving high enriched uranyl nitrate solution with and without cadmium nitrate as a soluble neutron absorber. The critical experiments analyzed include two types of cylindrical vessels with 24.18 and 29.16 cm in diameters. The vessels were reflected with water and in some cases with water containing dissolved cadmium nitrate. The uranium concentration ranged from 482 to 529 g/l, and cadmium concentration in the uranyl nitrate solution ranged from 0.0 to 11.31 g/l. The cadmium concentration in the reflector solution ranged from 0.0 to 15.16 g/l. Using MCNP and KENO-V.a, complete three-dimensional models were created for the two vessels filled with the uranyl nitrate solution and reflector solution. A series of criticality calculations were performed with KENO-V.a, MCNP4b, and MCNP5. In general, good agreement between KENO-V.a and MCNP4b was observed. However, MCNP5 results show consistently lower values compared with MCNP4b results with the maximum difference of 1.2 %. This ICSBEP supported evaluation provides valuable data for the effect of soluble neutron absorber (cadmium nitrate) on the criticality safety of high-enriched uranyl nitrate solution. These data can also be used in determining critical controls and for validation of the calculation methods.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC07-99ID-13727
- OSTI ID:
- 911571
- Report Number(s):
- INL/CON-05-01002; TRN: US0800014
- Resource Relation:
- Conference: PHYSOR-2006 Topical Meeting, Vancouver (Canada), 10-14 Sep 2006
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nuclear criticality safety calculations for a K-25 site vacuum cleaner
Evaluation of a Potassium Filled UO2 Core in a Beryllium- ??eflected Space Reactor