Criticality considerations for /sup 233/U fuels in an HTGR fuel refabrication facility

Technical Report · Sun Jan 01 00:00:00 EST 1978

DOI:https://doi.org/10.2172/5230200· OSTI ID:5230200

McNeany, S. R.; Jenkins, J. D.

Eleven /sup 233/U solution critical assemblies spanning an H//sup 233/U ratio range of 40 to 2000 and a bare metal /sup 233/U assembly have been calculated with the ENDF/B-IV and Hansen-Roach cross sections. The results from these calculations are compared with the experimental results and with each other. An increasing disagreement between calculations with ENDF/B and Hansen-Roach data with decreasing H//sup 233/U ratio was observed, indicative of large differences in their intermediate energy cross sections. The Hansen-Roach cross sections appeared to give reasonably good agreement with experiments over the whole range; whereas the ENDF/B calculations yielded high values for k/sub eff/ on assemblies of low moderation. It is concluded that serious problems exist in the ENDF/B-IV representation of the /sup 233/U cross sections in the intermediate energy range and that further evaluation of this nuclide is warranted. In addition, it is recommended that an experimental program be undertaken to obtain /sup 233/U criticality data at low H//sup 233/U ratios for verification of generalized criticality safety guidelines. Part II of this report presents the results of criticality calculations on specific pieces of equipment required for HTGR fuel refabrication. In particular, fuel particle storage hoppers and resin carbonization furnaces are criticality safe up to 22.9 cm (9.0 in.) in diameter providing water or other hydrogenous moderators are excluded. In addition, no criticality problems arise due to accumulation of particles in the off-gas scrubber reservoirs provided reasonable administrative controls are exercised.

• Research Organization: Lovelace Foundation for Medical Education and Research, Albuquerque, NM (USA). Dept. of Aerosol Physics
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5230200
• Report Number(s): ORNL/TM-6136
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CARBONIZATION
CHEMICAL REACTIONS
CRITICALITY
CRYOGENIC FLUIDS
DECOMPOSITION
ELEMENTS
EVEN-ODD NUCLEI
FLUIDS
FUEL CYCLE
FUEL FABRICATION PLANTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAVY NUCLEI
HTGR TYPE REACTORS
HYDROGEN
ISOTOPE RATIO
ISOTOPES
NONMETALS
NUCLEAR FACILITIES
NUCLEI
Nuclear Criticality Safety Program (NCSP)
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
RADIOISOTOPES
REACTORS
RESINS
STORAGE
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES