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DOE OSTI2019

The Effect of Glass Chemistry on Caesium Volatility in Iron Phosphate Glass Systems - 19344

The UK currently has a stockpile of 99,000 m{sup 3} of intermediate level waste (ILW), with this figure expected to rise to 191,000 m{sup 3} by 2125. Current immobilisation options include cementation and thermal treatment, with cementation being the preferred candidate due to the simplicity of processing. However, thermal processing such as vitrification could offer significant volume reductions, up to 75 % for some waste-streams. In comparison, cementation is generally associated with a volume increase, with a typical waste package seeing a volume increase of 200 - 400 %. For vitrification to be accepted as the preferred treatment option of ILW in the UK, the issue of volatility during the vitrification process must be addressed. Volatile components of ILW such as Cs-137 and Sr-90 account for almost 50 % of the current total radioactivity produced by the UK's ILW stockpile. Therefore, the efficient retention of these elements into the glass immobilisation medium must be considered. Various approaches can be employed when trying to increase volatile retention, however this project has focussed on the influence of glass chemistry on volatility. A series of iron phosphate glasses containing 5 mol % of B{sub 2}O{sub 3}, MnO and ZnO have been produced, where additives have been substituted in place of Fe{sub 2}O{sub 3} in a standard 40Fe{sub 2}O{sub 3}-60P{sub 2}O{sub 5} system. All glass samples were characterised using Raman spectroscopy, SEM-EDX, thermal analysis, XRD and XRF. The glasses were then doped with caesium carbonate and re-melted in the system described below. A simple off-gas system has been developed and commissioned to capture and characterise volatiles released from the glass during melting. The off-gas system has been refined several times, with the most recent design comprising of a sealed stainless steel system, connected to two gas washing bottles containing 150 ml of 50 % nitric acid. Nitrogen gas is passed through the system for the duration of the experiment at a flow rate of ∼ 0.9 L/min to ensure efficient carryover of the volatiles released from the glass melt into the solutions in the gas washing bottles. The total retention of the volatiles can be measuring by analysing the contents of the gas washing bottles using ICP-MS and XRF of the final glass product. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2026

Hot Hydrogen Exposure of U x Zr 1-x C y Nuclear Fuel: The Influence of Composition and Density

Refractory carbide nuclear fuel has been one of the most promising fuel candidates for space nuclear propulsion due to its high melting point, temperature stability, and compatibility in a hot hydrogen environment. In this study, U x Zr 1-x C y fuel was produced by means of a carbothermic reduction process in different UC compositions including 5,10, 20, and 30 at.% UC in the fuel compound. The powder feedstock was consolidated via direct current sintering with densities up to 97% of the theoretical density. The samples with different U x Zr 1-x C y compositions were exposed to hot hydrogen at 2600 K for a cumulative time of 300 min. The samples were characterized by SEM, XRD, density, and measured for mass losses. The high-density samples displayed improved performance in hot hydrogen by minimizing porous sites and reducing areas of direct contact with hydrogen gas, leading to reduced mass losses. Variations in sample density proved to induce large changes in mass loss rates, increasing them up to 90%. The compositions with higher UC content reported the largest mass losses in the study. The loss of uranium occurred primarily at the surfaces exposed to the hot hydrogen where changes in the lattice constant confirmed losses exceeding 50% of the initial UC content in higher compositions, specifically to U 0.3 Zr 0.7 C y . XRD analyses revealed the presence of UH 3 in U 0.3 Zr 0.7 C y suggesting that metallic uranium formed inside the sample as a product of carbon losses. High-density U x Zr x-1 C y fuel with UC concentrations at or below 20 at.% UC exhibited stability and negligible density changes in a high temperature hydrogen environment.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2015

Stationary Liquid Fuel Fast Reactor

For effective burning of hazardous transuranic (TRU) elements of used nuclear fuel, a transformational advanced reactor concept named SLFFR (Stationary Liquid Fuel Fast Reactor) was proposed based on stationary molten metallic fuel. The fuel enters the reactor vessel in a solid form, and then it is heated to molten temperature in a small melting heater. The fuel is contained within a closed, thick container with penetrating coolant channels, and thus it is not mixed with coolant nor flow through the primary heat transfer circuit. The makeup fuel is semi- continuously added to the system, and thus a very small excess reactivity is required. Gaseous fission products are also removed continuously, and a fraction of the fuel is periodically drawn off from the fuel container to a processing facility where non-gaseous mixed fission products and other impurities are removed and then the cleaned fuel is recycled into the fuel container. A reference core design and a preliminary plant system design of a 1000 MWt TRU- burning SLFFR concept were developed using TRU-Ce-Co fuel, Ta-10W fuel container, and sodium coolant. Conservative design approaches were adopted to stay within the current material performance database. Detailed neutronics and thermal-fluidic analyses were performed to develop a reference core design. Region-dependent 33-group cross sections were generated based on the ENDF/B-VII.0 data using the MC2-3 code. Core and fuel cycle analyses were performed in theta-r-z geometries using the DIF3D and REBUS-3 codes. Reactivity coefficients and kinetics parameters were calculated using the VARI3D perturbation theory code. Thermo-fluidic analyses were performed using the ANSYS FLUENT computational fluid dynamics (CFD) code. Figure 0.1 shows a schematic radial layout of the reference 1000 MWt SLFFR core, and Table 0.1 summarizes the main design parameters of SLFFR-1000 loop plant. The fuel container is a 2.5 cm thick cylinder with an inner radius of 87.5 cm. The fuel container is penetrated by twelve hexagonal control assembly (CA) guide tubes, each of which has 3.0 mm thickness and 69.4 mm flat-to-flat outer distance. The distance between two neighboring CA guide tube is selected to be 26 cm to provide an adequate space for CA driving systems. The fuel container has 18181 penetrating coolant tubes of 6.0 mm inner diameter and 2.0 mm thickness. The coolant tubes are arranged in a triangular lattice with a lattice pitch of 1.21 cm. The fuel, structure, and coolant volume fractions inside the fuel container are 0.386, 0.383, and 0.231, respectively. Separate steel reflectors and B4C shields are used outside of the fuel container. Six gas expansion modules (GEMs) of 5.0 cm thickness are introduced in the radial reflector region. Between the radial reflector and the fuel container is a 2.5 cm sodium gap. The TRU inventory at the beginning of equilibrium cycle (BOEC) is 5081 kg, whereas the TRU inventory at the beginning of life (BOL) was 3541 kg. This is because the equilibrium cycle fuel contains a significantly smaller fissile fraction than the LWR TRU feed. The fuel inventory at BOEC is composed of 34.0 a/o TRU, 41.4 a/o Ce, 23.6 a/o Co, and 1.03 a/o solid fission products. Since uranium-free fuel is used, a theoretical maximum TRU consumption rate of 1.011 kg/day is achieved. The semi-continuous fuel cycle based on the 300-batch, 1- day cycle approximation yields a burnup reactivity loss of 26 pcm/day, and requires a daily reprocessing of 32.5 kg of SLFFR fuel. This yields a daily TRU charge rate of 17.45 kg, including a makeup TRU feed of 1.011 kg recovered from the LWR used fuel. The charged TRU-Ce-Co fuel is composed of 34.4 a/o TRU, 40.6 a/o Ce, and 25.0 a/o Co.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2019

The Effect of Glass Chemistry on Caesium Volatility

The UK currently has 99,000 m3 of intermediate level waste (ILW). The current preferred treatment route is cementation. However, thermal treatment could offer a better long term option due to higher waste loading and lower storage costs. This project will focus on volatile retention in the vitrification process to make thermal treatment a more viable option. A series of iron phosphate base glasses were prepared with the nominal molar composition xM{sub y}O{sub z}(40 - x)Fe{sub 2}O{sub 3}-P{sub 2}O{sub 5} (M{sub y}O{sub z} = B{sub 2}O{sub 3}, MnO, ZnO with x = 5%). Samples are given names of the form IPG-1-X5 where X = B, Mn or Zn. For all batches, reagents were weighed and mechanically mixed to produce 150 g of glass. melted at 1150 deg. C for 3 h, Samples were immediately transferred to an annealing furnace and annealed at 450 deg. C for 1 h before being cooled to room temperature at 1 deg. C min{sup -1}. 75 g batches was produced with a target of 2 wt.% caesium oxide. Each batch was placed into a mullite crucible and placed in the sealed system seen below. Each canister was placed into a top-loading resistance furnace and ramped to 950 deg. C at a rate of 3 deg. C min{sup -1} under a nitrogen atmosphere with a flowrate of ∼0.9 L min{sup -1}. The samples were held at this temperature for 3 h before power to the furnace was removed and the system allowed to cool naturally. Once cool, the steel canister was opened and the entire apparatus (steel canister, mullite crucible and tubing) was washed through with ∼50 ml of 0.5 M HNO{sub 3} to allow for a complete mass balance of the caesium species. A series of Iron Phosphate glasses have been produced and characterised to investigate the influence of glass chemistry on the volatility of caesium. All glasses were doped with ∼2 wt.% Cs{sub 2}O and re-melted at 950 deg. C for 3 hours in a specially designed furnace set-up. Results of these experiments showed that the addition of 5 mol. % ZnO greatly increased the retention of Cs{sub 2}O whilst B{sub 2}O{sub 3} was detrimental to the Cs{sub 2}O retention. A series of iron phosphate based glasses have been produced with 5 mol.% additions of B{sub 2}O{sub 3}, MnO and ZnO, substituted in place of Fe{sub 2}O{sub 3}. All samples were analysed before and after being doped and re-melted with a 2 wt.% addition of Cs{sub 2}O. The effect of each additive on the base glass has been reported showing that both B{sub 2}O{sub 3} and ZnO increase the glass transition temperature, whilst MnO additions decrease the thermal stability of the glass. The Q-speciation of the glasses was investigated, and the results showed that the additives did not significantly influence the Q-speciation in comparison to the base glass. It has been shown that the addition of ZnO dramatically increases the retention of Cs during re-melting by almost a factor of 10 in comparison to the base glass, whilst the addition of MnO addition increased the caesium retention but only by a factor of ∼3. The addition of B{sub 2}O{sub 3} had a detrimental effect on the volatility in comparison to the 40Fe{sub 2}O{sub 3}-60P{sub 2}O{sub 5} base glass.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗