Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle

Hill, R. N.; Wade, David; Liaw, J.R.; Fujita, E.K.

doi:10.13182/nse121-17

Cited by 29 publications

(7 citation statements)

References 3 publications

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“…The small magnitude of the Doppler coefficient is typical for metallic-fueled cores, such as the IFR, where, for plutonium burning, Hill et al, [1995] reported a value of the Doppler coefficient of ~ -0.05¢/K.…”

Section: Reactivity Coefficients and Self-controllability Criteriamentioning

confidence: 98%

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Todreas¹,

Hejzlar²

2008

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This is the final report under award DE-FC07-06ID14733, Project No. 06-040. Conceptual designs of lead-cooled and liquid salt-cooled fast flexible conversion ratio reactors were developed. Both concepts have cores rated at 2400MWt placed in a largepool-type vessel with dual-free level, which also contains four intermediate heat exchangers (IHXs) coupling a primary coolant to a compact and efficient supercritical CO 2 Brayton cycle power conversion system. Decay heat is removed passively using an enhanced Reactor Vessel Auxiliary Cooling System (RVACS) and a Passive Secondary Auxiliary Cooling System (PSACS). The most important findings were that (1) it is feasible to design the lead-cooled and salt-cooled reactor with the flexible conversion ratio (CR) in the range of CR=0 and CR=1 in a manner that achieves inherent reactor shutdown in unprotected accidents, (2) the salt-cooled reactor requires Lithium thermal Expansion Modules (LEM) to overcome the inherent salt coolant's large positive coolant temperature reactivity coefficient, (3) the preferable salt for fast spectrum high power density cores is NaCl-KCl-MgCl 2 as opposed to fluoride salts due to its better thermalhydraulic and neutronic characteristics, and (4) both reactor concepts achieve about 30% higher power density than the gas-cooled fast reactor, but attain power density 3 times smaller than that of the sodium-cooled reactor.

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Section: Reactivity Coefficients and Self-controllability Criteriamentioning

confidence: 98%

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Todreas¹,

Hejzlar²

2008

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“…The second case is based on the moderate burner design [20], with control assemblies and gas expansion modules represented, but with no axial reflectors nor shields, and a 0.6 m active core region. The radial core layout is shown in Fig.…”

Section: Ivb Case 2 -Axially Uniform Corementioning

confidence: 99%

“…The third case is the moderate burner design [20] with axial reflectors and shields, and the 42 cm active core. The radial layout is again given by Fig.…”

Section: Ivc Case 3 -Full Core With Axial Reflectorsmentioning

confidence: 99%

Final Report for the NERI Project

Lee¹

2009

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a manuscript summarizing the fuel cycle optimization algorithms for the sodium-cooled fast reactor (SFR) developed under the grant. These three latest papers are attached to the report. Summary of research accomplishments Task Optimization of fast rector transmuterWith the objective to perform systematic optimization of SFR transmuters, we developed a general fuel cycle optimization methodology that could be applied to the optimization of fuel cycles both for SFRs and pressurized water reactors (PWRs). The key features of the optimization algorithms include:(1) The optimization algorithms are based on the calculus of variations that allows for a systematic augmentation of desired objective function typically expressed in terms of end-of-cycle (EOC) fuel cycle attributes, (2)The Lagrange multipliers introduced in the augmentation process allows for direct representation of system constraints, e.g., the power peaking factor constraint, (3) A first-order variation of the augmented objective function yields the necessary condition for optimality together with Euler-Lagrange equations for the Lagrange multipliers cast in the form of adjoint system equations, (4) The adjoint flux and depletion equations are solved backward from EOC to beginning-of-cycle (BOC), with discontinuities introduced in the adjoint neutron flux at the constraint boundaries, (5) The adjoint flux, combined with the forward flux, provides the search directions for the control variables, e.g., transuranics (TRU) enrichment or burnable absorber (BA) placement, and (6) The combination of forward diffusion-depletion calculations and backward adjoint flux-depletion calculations is repeated until the objective function is minimized. The deterministic algorithms may be initiated from arbitrary core configurations and typically converge in a few iterations to yield optimal configurations desired. This is to be contrasted with many of the popular stochastic optimization algorithms that require 2 10 4~1 0 5 iterations before an optimal configuration is attained. Furthermore, through a separate backward diffusion theory algorithm, the power peaking constraints are rigorously satisfied. The optimization algorithm for SFR transmuter cases systematically yields an optimized core configuration with a reduced power peaking factor and lower reactivity swing over a fuel cycle. Similarly, the PWR optimization algorithm applied to the AP600 design yields a lower radial peaking factor than that presented in the Standard Safety Analysis Report, together with a reduced number of BA rods required. This implies that the improved design allows for (a) a higher power density, (b) an increased cycle length due to a reduction in the residual BA penalty at EOC, and (c) savings in the BA cost. Two doctoral dissertations were completed under Task 1.Publications resulting from Task 1 are listed below:1. R. T. Sorensen, J. C. Davis, and J. C. Lee, "Systematic Method for Optimizing Plutonium Transmutation in LWRs," Trans. Am. Nucl. Soc., 95, 217 (2006). Task 2. Development of equ...

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“…This design was developed in the former U.S. fast reactor program by General Electric and Argonne National Laboratory; conventional and burner configurations for a weapons plutonium disposition mission are described in Ref. 7. The ALMR burner design utilizes standard fertile fuel formsternary metal U/TRU-10Zr alloy with maximum TRU content of ~30%.…”

Section: Description Of Transmutation Systemsmentioning

confidence: 99%

Multiple Tier Fuel Cycle Studies for Waste Transmutation

Hill

Taiwo

Stillman

et al. 2002

10th International Conference on Nuclear Engineering, Volume 2

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As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (~0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system.

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Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle

Cited by 29 publications

References 3 publications

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Final Report for the NERI Project

Multiple Tier Fuel Cycle Studies for Waste Transmutation

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