Fission product release. Progress report, April 1-June 30, 1980

Technical Report · Mon Sep 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5086631· OSTI ID:5086631

Norris, A E ^[1]

---

1. comp.

The analysis of data collected from nuclear waste leaching experiments is under way to determine what differences are important when one spent fuel element wafer is leached under aqueous reducing conditions while the other is leached under oxidizing conditions. The concentrations of radioactive species in the leachant solutions are being investigated in terms of dissolution congruent with that of the UO/sub 2/ matrix and, for the lanthanide and actinide elements, in terms of precipitation reactions that result in limiting the concentrations of the species in solution. The concentrations of uranium and plutonium is solution under reducing conditions, however, are much higher than would be expected from the oxygen fugacity of the leachant derived from the measured Eh value. It is inferred that the actual reducing conditions in this pH 4 solution were much more oxidizing than desired for the experiment. The solubility of pure uraninite measured in deionized water was used in conjunction with thermodynamic calculations to infer that the oxygen fugacity in the apparatus, which differed from that used for the spentfuel leaching, was approx. 10/sup -50/ bars and that CO/sub 2/ was either absent or present in such low concentrations that the UO/sub 2/ solubility was not appreciably affected. 14 figures.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5086631
• Report Number(s): LA-8539-PR; ONWI/Sub-80/E511-01200-7
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
SPENT FUELS
FISSION PRODUCT RELEASE
LEACHING
AMERICIUM 241
ANTIMONY 125
AQUEOUS SOLUTIONS
CESIUM 137
CESIUM 144
EUROPIUM 154
OXIDATION
PH VALUE
PLUTONIUM 239
REDUCTION
RESEARCH PROGRAMS
ROBINSON-2 REACTOR
SOLUBILITY
STRONTIUM 90
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
ALPHA DECAY RADIOISOTOPES
AMERICIUM ISOTOPES
ANTIMONY ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BETA-PLUS DECAY RADIOISOTOPES
CESIUM ISOTOPES
CHALCOGENIDES
CHEMICAL REACTIONS
DISPERSIONS
DISSOLUTION
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EUROPIUM ISOTOPES
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FUELS
HEAVY NUCLEI
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOTOPES
MATERIALS
MIXTURES
NUCLEAR FUELS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM ISOTOPES
POWER REACTORS
PWR TYPE REACTORS
RADIOISOTOPES
RARE EARTH ISOTOPES
RARE EARTH NUCLEI
REACTOR MATERIALS
REACTORS
SECONDS LIVING RADIOISOTOPES
SEPARATION PROCESSES
SOLUTIONS
STRONTIUM ISOTOPES
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
053000* - Nuclear Fuels- Environmental Aspects
052002 - Nuclear Fuels- Waste Disposal & Storage