Optimization of Accelerator-driven Technology for LWR Waste Transmutation


Book Description

The role of accelerator-driven transmutation technology is examined in the context of the destruction of actinide waste from commercial light water reactors. It is pointed out that the commercial plutonium is much easier to use for entry-level nuclear weapons than weapons plutonium. Since commercial plutonium is easier to use, since there is very much more of it already, and since it is growing rapidly, the permanent disposition of commercial plutonium is an issue of greater importance than weapons plutonium. The minor actinides inventory, which may be influenced by transmutation, is compared in terms of nuclear properties with commercial and weapons plutonium and for possible utility as weapons material. Fast and thermal spectrum systems are compared as means for destruction of plutonium and the minor actinides. it is shown that the equilibrium fast spectrum actinide inventory is about 100 times larger than for thermal spectrum systems, and that there is about 100 times more weapons-usable material in the fast spectrum system inventory compared to the thermal spectrum system. Finally it is shown that the accelerator size for transmutation can be substantially reduced by design which uses the accelerator-produced neutrons only to initiate the unsustained fission chains characteristic of the subcritical system. The analysis argues for devoting primary attention to the development of thermal spectrum transmutation technology. A thermal spectrum transmuter operating at a fission power of 750-MWth fission power, which is sufficient to destroy the actinide waste from one 3,000-MWth light water reactor, may be driven by a proton beam of 1 GeV energy and a current of 7 mA. This accelerator is within the range of realizable cyclotron technology and is also near the size contemplated for the next generation spallation neutron source under consideration by the US, Europe, and Japan.




Nuclear Wastes


Book Description

Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.







Transmutation of High-level Radioactive Waste and Production of 233U Using an Accelerator-driven Reactor


Book Description

Reactor safety, the disposal of high-level nuclear waste, and nonproliferation of nuclear material for military purposes are the problems of greatest concern for nuclear energy. Technologies for accelerators developed in the field of high-energy physics can contribute to solving these problems. For reactor safety, especially for that of a Na-cooled fast reactor, the use of an accelerator, even a small one, can enhance the safety using a slightly subcritical reactor. There is growing concern about how we can deal with weapons-grade Pu, and about the large amount of Pu accumulating from the operation of commercial reactors. It has been suggested that this Pu could be incinerated, using the reactor and a proton accelerator. However, because Pu is a very valuable material with future potential for generating nuclear energy, we should consider transforming it into a proliferation-resistant material that cannot be used for making bombs, rather than simply eliminating the Pu. An accelerator-driven fast reactor (700 MWt), run in a subcritical condition, and fueled with MOX can generate 233U more safely and efficiently than can a critical reactor. We evaluate the production of 233U, 239Pu, and the transmutation of the long-lived fission products of 99Tc and 129I, which are loaded with YH{sub 1.7} between the fast core and blanket, by reducing the conversion factor of Pu to 233U. And we assessed the rates of radiation damage, hydrogen production, and helium production in a target window and in the surrounding vessel.




Accelerator-driven Sub-critical Target Concept for Transmutation of Nuclear Wastes


Book Description

A means of transmuting key long-lived nuclear wastes, primarily the minor actinides (Np, Am, Cm) and iodine, using a hybrid proton accelerator and sub-critical lattice, is proposed. By partitioning the components of the light water reactor (LWR) spent fuel and by transmuting key elements, such as the plutonium, the minor actinides, and a few of the long-lived fission products, some of the most significant challenges in building a waste repository can be substantially reduced. The proposed machine, based on the described PHOENIX Concept, would transmute the minor actinides and the iodine produced by 75 LWRs, and would generate usable electricity (beyond that required to run the large accelerator) of 850 MW{sub e}. 19 refs., 20 figs.




Assessment of General Atomics Accelerator Transmutation of Waste Concept Based on Gas-turbine-modular Helium Cooled Reactor Technology


Book Description

An assessment has been performed for an Accelerator Transmutation of Waste (ATW) concept based on the use of the high temperature gas reactor technology. The concept has been proposed by General Atomics for the ATW system. The assessment was jointly conducted at Argonne National Laboratory (ANL) and Los Alamos national laboratory to assess and to define the potential candidates for the ATW system. This report represents the assessment work performed at ANL. The concept uses recycled light water reactor (LWR)-discharge-transuranic extracted from irradiated oxide fuel in a critical and sub-critical accelerator driven gas-cooled transmuter. In this concept, the transmuter operates at 600 MWt first in the critical mode for three cycles and then operates in a subcritical accelerator-driven mode for a single cycle. The transmuter contains both thermal and fast spectrum transmutation zones. The thermal zone is fueled with the TRU oxide material in the form of coated particles, which are mixed with graphite powder, packed into cylindrical compacts, and loaded in hexagonal graphite blocks with cylindrical channels; the fast zone is fueled with TRU-oxide material in the form of coated particles without the graphite powder and the graphite blocks that has been burned in the thermal region for three critical cycles and one additional accelerator-driven cycle. The fuel loaded into the fast zone is irradiated for four additional cycles. This fuel management scheme is intended to achieve a high Pu isotopes consumption in the thermal spectrum zone, and to consume the minor actinides in the fast-spectrum zone. Monte Carlo and deterministic codes have been used to assess the system performance and to determine the feasibility of achieving high TRU consumption levels. The studies revealed the potential for high consumption of Pu-239 (97%), total Pu (71%) and total TRU (64%) in the system. The analyses confirmed the need for burnable absorber for both suppressing the initial excess reactivity and ensuring a negative temperature coefficient under all operating conditions. Additionally, current results suggest that it may be preferable to use a double strata thermal critical system and fast subcritical system to achieve nearly complete destruction of the TRU oxide fuel. The report gives a general description of the system proposed by General Atomics. The major design parameters (degrees of freedom), which can be altered to optimize the system design, and the constraints, which guide the design and the optimization studies are described. The deterministic and the Monte Carlo neutronics codes and models used for the neutronics analysis and assessment are presented. The results of fuel block and whole-core parametric studies performed to understand the physics are given including the effect of various fuel management schemes on the system performance. A point design is described including the system performance results for a single-batch and three-batch loading schemes. The major design issues, which need to be addressed during further studies, are discussed.










High Power Ring Methods and Accelerator Driven Subcritical Reactor Application


Book Description

High power proton accelerators allow providing, by spallation reaction, the neutron fluxes necessary in thesynthesis of fissile material, starting from Uranium 238 or Thorium 232. This is the basis of the concept ofsub-critical operation of a reactor, for energy production or nuclear waste transmutation, with the objective ofachieving cleaner, safer and more efficient process than today's technologies allow.Designing, building and operating a proton accelerator in the 500-1000 MeV energy range, CW regime,MW power class still remains a challenge nowadays. There is a limited number of installations at presentachieving beam characteristics in that class, e.g., PSI in Villigen, 590 MeV CW beam from a cyclotron, SNS inOakland, 1 GeV pulsed beam from a linear accelerator, in addition to projects as the ESS in Europe, a 5 MWbeam from a linear accelerator.Furthermore, coupling an accelerator to a sub-critical nuclear reactor is a challenging proposition: some ofthe key issues/requirements are the design of a spallation target to withstand high power densities as well asensure the safety of the installation.These two domains are the grounds of the PhD work: the focus is on the high power ring methods inthe frame of the KURRI FFAG collaboration in Japan: upgrade of the installation towards high intensityis crucial to demonstrate the high beam power capability of FFAG. Thus, modeling of the beam dynamicsand benchmarking of different codes was undertaken to validate the simulation results. Experimental resultsrevealed some major losses that need to be understood and eventually overcome.By developing analytical models that account for the field defects, one identified major sources of imperfectionin the design of scaling FFAG that explain the important tune variations resulting in the crossing of severalbetatron resonances. A new formula is derived to compute the tunes and properties established that characterizethe effect of the field imperfections on the transverse beam dynamics. The results obtained allow to developa correction scheme to minimize the tune variations of the FFAG. This is the cornerstone of a new fixed tunenon-scaling FFAG that represents a potential candidate for high power applications.As part of the developments towards high power at the KURRI FFAG, beam dynamics studies have toaccount for space charge effects. In that framework, models have been installed in the tracking code ZGOUBIto account for the self-interaction of the particles in the accelerator. Application to the FFAG studies is shown.Finally, one focused on the ADSR concept as a candidate to solve the problem of nuclear waste. In orderto establish the accelerator requirements, one compared the performance of ADSR with other conventionalcritical reactors by means of the levelized cost of energy. A general comparison between the different acceleratortechnologies that can satisfy these requirements is finally presented.In summary, the main drawback of the ADSR technology is the high Levelized Cost Of Energy comparedto other advanced reactor concepts that do not employ an accelerator. Nowadays, this is a show-stopper forany industrial application aiming at producing energy (without dealing with the waste problem). Besides, thereactor is not intrinsically safer than critical reactor concepts, given the complexity of managing the targetinterface between the accelerator and the reactor core.