Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold: first to verify and validate each of the code packages of the project partners, adapted for liquid-fueled reactors, and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor (MSFR). The MSFR operates with the thorium fuel cycle and can be started with 233U-enriched U and/or TRU elements as initial fissile load. All three compositions were covered by the present benchmark. The calculations have confirmed that the MSFR has very favorable characteristics not present in other Gen4 fast reactors, like strong negative temperature and void reactivity coefficients, a low-fissile inventory, a reduced long-lived waste production and its burning capacities of nuclear waste produced in currently operational reactors.

A disruptive approach to eliminating weapon-grade plutonium - Pu burning in a molten salt fast reactor

The successful implementation of disarmament treaties of the last centuries has led to significant amounts of weapon-grade Plutonium which are currently stored in high security storage facilities. Disposing this Plutonium should be seen as 'good housekeeping' avoiding unnecessary costs and the hazards of storing this material indefinitely. In addition, the disarmament is only brought to a successful end when the Plutonium isn't available for the production of new weapons anymore. We propose a disruptive approach for Plutonium disposition and demonstrate the feasibility in a neutronic study. Burning of weapon-grade Plutonium in a molten salt fast reactor is significantly more efficient than in the studied other reactors, while efficient process design has the potential to reduce the security concerns significantly. The proposed system could turn about 1.25 tons of weapon-grade Plutonium into electric energy worth £ 0.5 to 1 billion/year, depending on the electricity price while avoiding the hassle and eliminating the risk of high security Plutonium storage. In conclusion, burning of the weapon-grade Plutonium resulting from disarmament could be an economically very attractive approach to reduce the nuclear threat.

Demand driven salt clean-up in a molten salt fast reactor - Defining a priority list

The PUREX technology based on aqueous processes is currently the leading reprocessing technology in nuclear energy systems. It seems to be the most developed and established process for light water reactor fuel and the use of solid fuel. However, demand driven development of the nuclear system opens the way to liquid fuelled reactors, and disruptive technology development through the application of an integrated fuel cycle with a direct link to reactor operation. The possibilities of this new concept for innovative reprocessing technology development are analysed, the boundary conditions are discussed, and the economic as well as the neutron physical optimization parameters of the process are elucidated. Reactor physical knowledge of the influence of different elements on the neutron economy of the reactor is required. Using an innovative study approach, an element priority list for the salt clean-up is developed, which indicates that separation of Neodymium and Caesium is desirable, as they contribute almost 50% to the loss of criticality. Separating Zirconium and Samarium in addition from the fuel salt would remove nearly 80% of the loss of criticality due to fission products. The theoretical study is followed by a qualitative discussion of the different, demand driven optimization strategies which could satisfy the conflicting interests of sustainable reactor operation, efficient chemical processing for the salt clean-up, and the related economic as well as chemical engineering consequences. A new, innovative approach of balancing the throughput through salt processing based on a low number of separation process steps is developed. Next steps for the development of an economically viable salt clean-up process are identified.

An innovative way of thinking nuclear waste management - Neutron physics of a reactor directly operating on SNF

A solution for the nuclear waste problem is the key challenge for an extensive use of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source. Partitioning and Transmutation (P&T) promises a solution for improved waste management. Current strategies rely on systems designed in the 60’s for the massive production of plutonium. We propose an innovative strategic development plan based on invention and innovation described with the concept of developments in s-curves identifying the current boundary conditions, and the evolvable objectives. This leads to the ultimate, universal vision for energy production characterized by minimal use of resources and production of waste, while being economically affordable and safe, secure and reliable in operation. This vision is transformed into a mission for a disruptive development of the future nuclear energy system operated by burning of existing spent nuclear fuel (SNF) without prior reprocessing. This highly innovative approach fulfils the sustainability goals and creates new options for P&T. A proof on the feasibility from neutronic point of view is given demonstrating sufficient breeding of fissile material from the inserted SNF. The system does neither require new resources nor produce additional waste, thus it provides a highly sustainable option for a future nuclear system fulfilling the requests of P&T as side effect. In addition, this nuclear system provides enhanced resistance against misuse of Pu and a significantly reduced fuel cycle. However, the new system requires a demand driven rethinking of the separation process to be efficient.

Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T) could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET

In the present feasibility study the system code ATHLET, which originates from nuclear engineering, is applied to a parabolic trough test facility. A model of the DISS (DIrect Solar Steam) test facility at Plataforma Solar de Almería in Spain is assembled and the results of the simulations are compared to measured data and the simulation results of the Modelica library “DissDyn”. A profound comparison between ATHLET Mod 3.0 Cycle A and the “DissDyn” library reveals the capabilities of these codes. The calculated mass and energy balance in the ATHLET simulations are in good agreement with the results of the measurements and confirm the applicability for thermodynamic simulations of DSG processes in principle. Supplementary, the capabilities of the 6-equation model with transient momentum balances in ATHLET are used to study the slip between liquid and gas phases and to investigate pressure wave oscillations after a sudden valve closure.

Synthese und Untersuchung neuer 1λ5, 4λ5-Diphosphapentalen- und 1λ5,4λ5 - sowie 1λ5,5λ5-Diphosphaazulen-Systeme / Synthesis of New 1λ5,4λ5-Diphosphapentalene- and 1λ5,5λ5-Diphosphaazulene Systems

Bis[bis(dimethylamino)phosphino]acetylene (2a) and two molecules of dimethyl- and diethyl-acetylenedicarboxylate (1a /1b ) react in a criss-cross-cycloaddition to yield 1λ5 ,4λ5- diphosphapentalenes (3), which react further with 1 to yield a 1λ5 ,4λ5-diphosphaazulenes (5). A mechanism of both reactions is proposed. The reaction of 1λ5,4λ5-diphosphaazulene with 1a at high pressure yields 1,1,4,4-tetrakis(dimethylamino)-3,5,6,7,8 -pentakis(methoxycarbonyl)- 2-[1,2,2tris(methoxycarbonyl)ethenyl]-1λ5,4λ5 -diphosphaazulene (7). The reaction of bis(diphenylphosphino) acetylene (2c) with 1a yields 1,5a-dihydro-1-methoxy-(1-methoxycarbonylethinyl)- 3,3,7,7-tetraphenyl)-2-oxa-3λ5,7λ5 -diphosphacyclopenta[1,2,3-c,d]azulene- 4,5,5a,6,8,9-hexakis(methoxycarbonyl) (9) and 4-(diphenylphosphoryl)-5-[1,2-bis-(methoxycarbonyl)- ethylidene]-1λ5-phosphol-2,3-bis(methoxycarbonyl) (10)

On the use of a molten salt fast reactor to apply an idealized transmutation scenario for the nuclear phase out

In the view of transmutation of transuranium (TRU) elements, molten salt fast reactors (MSFRs) offer certain advantages compared to solid fuelled reactor types like sodium cooled fast reactors (SFRs). In the first part these advantages are discussed in comparison with the SFR technology, and the research challenges are analyzed. In the second part cycle studies for the MSFR are given for different configurations – a core with U-238 fertile, a fertile free core, and a core with Th-232 as fertile material. For all cases, the transmutation potential is determined and efficient transmutation performance for the case with thorium as a fertile material as well as for the fertile free case is demonstrated and the individual advantages are discussed. The time evolution of different important isotopes is analyzed. In the third part a strategy for the optimization of the transmutation efficiency is developed. The final aim is dictated by the phase out decision of the German government, which requests to put the focus on the determination of the maximal transmutation efficiency and on an as much as possible reduced leftover of transuranium elements at the end of the reactor life. This minimal leftover is achieved by a two step procedure of a first transmuter operation phase followed by a second deep burning phase. There the U-233, which is bred in the blanket of the core consisting of thorium containing salt, is used as feed. It is demonstrated, that transmutation rates up to more than 90% can be achieved for all transuranium isotopes, while the production of undesired high elements like californium is very limited. Additionally, the adaptations needed for the simulation of a MSFR, and the used tool HELIOS 1.10 is described.

An infrastructure for accurate characterization of single-event transients in digital circuits

We present the architecture and a detailed pre-fabrication analysis of a digital measurement ASIC facilitating long-term irradiation experiments of basic asynchronous circuits, which also demonstrates the suitability of the general approach for obtaining accurate radiation failure models developed in our FATAL project. Our ASIC design combines radiation targets like Muller C-elements and elastic pipelines as well as standard combinational gates and flip-flops with an elaborate on-chip measurement infrastructure. Major architectural challenges result from the fact that the latter must operate reliably under the same radiation conditions the target circuits are exposed to, without wasting precious die area for a rad-hard design. A measurement architecture based on multiple non-rad-hard counters is used, which we show to be resilient against double faults, as well as many triple and even higher-multiplicity faults. The design evaluation is done by means of comprehensive fault injection experiments, which are based on detailed Spice models of the target circuits in conjunction with a standard double-exponential current injection model for single-event transients (SET). To be as accurate as possible, the parameters of this current model have been aligned with results obtained from 3D device simulation models, which have in turn been validated and calibrated using micro-beam radiation experiments at the GSI in Darmstadt, Germany. For the latter, target circuits instrumented with high-speed sense amplifiers have been used for analog SET recording. Together with a probabilistic analysis of the sustainable particle flow rates, based on a detailed area analysis and experimental cross-section data, we can conclude that the proposed architecture will indeed sustain significant target hit rates, without exceeding the resilience bound of the measurement infrastructure.

Species conserved DNA damage response at the inactive human X chromosome

Chromatin modifications are long known as an essential part of the orchestrated response resulting in the repair of radiation-induced DNA double-strand breaks (DSBs). Only recently, however, the influence of the chromatin architecture itself on the DNA damage response has been recognised. Thus for heterochromatic DSBs the sensing and early recruitment of repair factors to the lesion occurs within the heterochromatic compartments, but the damage sites are subsequently relocated from the inside to the outside of the heterochromatin. While previous studies were accomplished at the constitutive heterochromatin of centromeric regions in mouse and flies, here we examine the DSB repair at the facultative heterochromatin of the inactive X chromosome (Xi) in humans. Using heavy ion irradiation we show that at later times after irradiation the DSB damage streaks bend around the Xi verifying that the relocation process is conserved between species and not specialised to repetitive sequences only. In addition, to measure chromatin relaxation at rare positions within the genome, we established live cell microscopy at the GSI microbeam thus allowing the aimed irradiation of small nuclear structures like the Xi. Chromatin decondensation at DSBs within the Xi is clearly visible within minutes as a continuous decrease of the DNA staining over time, comparable to the DNA relaxation revealed at DSBs in mouse chromocenters. Furthermore, despite being conserved between species, slight differences in the underlying regulation of these processes in heterochromatic DSBs are apparent.

An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies

A new analytical method is described to deal with the Leakage Environmental Effect for the cross section production. The method is based on the one dimensional analytical solution of the two-group diffusion equation for two adjacent, homogenized fuel assemblies. The high quality of the results for this highly efficient method is demonstrated for square fuel assemblies. In additional tests the limiting case for the transferability of the concept to the small hexagonal VVER-440 type fuel assemblies is shown.

Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR

The Light Water Reactor (LWR) dynamics code DYN3D is extended and adopted for the application to block-type High Temperature Gas-Cooled Reactor (HTGR). A procedure for the cross section generation for the HTGR core calculations was developed. The modified Reactivity-Equivalent Physical Transformation (RPT) approach is applied in order to eliminate the double-heterogeneity of HTGR fuel elements in the deterministic lattice calculations. A full core analysis of the reference simplified HTGR core is performed with DYN3D using macroscopic nodal cross sections provided by HELIOS.

The SP3 transport approximation is integrated into the multi-group DYN3D code to take anisotropy of the neutron flux and heterogeneity of the core more precisely into account. The SP3 method was developed for hexagonal geometry of the graphite blocks, where the hexagons are subdivided into triangular nodes.

A 3D heat conduction module coupled with a channel-type coolant flow model is implemented into the code. It is shown that there is significant redistribution of the produced heat by heat conduction between the graphite blocks.

[Special care units for the treatment of acutely ill, cognitively impaired geriatric patients in Germany]

During recent years, specialized wards have been established in geriatric hospital departments as a consequence of the growing need of special care for acutely ill older patients, who are also cognitively impaired. However, there are neither established standards nor any commonly agreed concept of care. A written survey among 12 specialized wards in Germany revealed some characteristics of these wards: extended geriatric assessment, special education of staff including validation and gerontopsychiatric issues, and particular equipment/architecture, such as hidden doors and group rooms, and in some cases loop tracks for walking, therapeutic facilities, and 'living rooms' on the wards. There is a wide variability with respect to the designation of these wards, the number of beds, length of stay, and admission criteria. It appears from this survey that there should be an exchange of empirical experience made on these wards, and there is a need of collaborative research on its usefulness.

The spectrum of PIG-A gene mutations in aplastic anemia/paroxysmal nocturnal hemoglobinuria (AA/PNH): a high incidence of multiple mutations and evidence of a mutational hot spot

Paroxysmal nocturnal hemoglobinuria (PNH) may arise during long-term follow- up of aplastic anemia (AA), and many AA patients have minor glycosylphosphatidylinositol (GPI) anchor-deficient clones, even at presentation. PIG-A gene mutations in AA/PNH and hemolytic PNH are thought to be similar, but studies on AA/PNH have been limited to individual cases and a few small series. We have studied a large series of AA patients with a GPI anchor-deficient clone (AA/PNH), including patients with minor clones, to determine whether their pattern of PIG-A mutations was identical to the reported spectrum in hemolytic PNH. AA patients with GPI anchor-deficient clones were identified by flow cytometry and minor clones were enriched by immunomagnetic selection. A variety of methods was used to analyze PIG-A mutations, and 57 mutations were identified in 40 patients. The majority were similar to those commonly reported, but insertions in the range of 30 to 88 bp, due to tandem duplication of PIG-A sequences, and deletions of more than 10 bp were also seen. In 3 patients we identified identical 5-bp deletions by conventional methods. This prompted the design of mutation-specific polymerase chain reaction (PCR) primers, which were used to demonstrate the presence of the same mutation in an additional 12 patients, identifying this as a mutational hot spot in the PIG-A gene. Multiple PIG-A mutations have been reported in 10% to 20% of PNH patients. Our results suggest that the large majority of AA/PNH patients have multiple mutations. These data may suggest a process of hypermutation in the PIG-A gene in AA stem cells.

Identification of novel polymorphisms in intron 7 of the human p53 gene in acute myeloid leukemia and healthy donors

Screening for mutations by PCR-SSCP in exons 5 to 9 of the p53 gene in 38 bone marrow or peripheral blood specimens of patients with acute myeloid leukemia (AML) showed abnormal shifts in 9 cases. One reflected a mutation in exon 8, whereas in the other cases there were no exonic mutations identified by sequencing. As PCR primers were chosen annealing in the introns flanking the exon region, following sequencing of the encompassing introns identified 5 base substitutions at various sites in intron 7. Two of them have been described previously [1] and 3 novel polymorphisms could be identified. To determine whether these polymorphisms are linked to the pathogenesis of AML, we screened peripheral blood specimens of 26 healthy controls. We found identical base substitutions in 6 out of 26 controls. Our data suggest that these polymorphisms are not related to the pathogenesis of AML.

Cyclosporin A inhibits cytokine-induced proliferation in B-chronic lymphocytic leukemia

We investigated the effects of the immunosuppressant cyclosporin A (CsA) on proliferation of neoplastic B-cells from patients with B-chronic lymphocytic leukemia (B-CLL). Cell growth was induced in vitro by tumor necrosis factor alpha (TNF-alpha (8/16), interleukin 2 (IL-2 (9/16) or both (7/16), in 4 cases spontaneous proliferation was observed. We were able to demonstrate that CsA inhibits cytokine-induced proliferation, as measured by [3H]-thymidine incorporation, in all cases responsive to TNF-alpha or IL-2 as well as in spontaneous proliferation. CsA did not increase the fraction of trypan blue positive cells or apoptosis. Growth inhibition by CsA occurred in a dose dependent manner: 100 ng/ml CsA was the optimal concentration which blocked about 90% of cytokine induced or spontaneous proliferation. We could also demonstrate that the effect of CsA was reversible and that no blocking effect was observed when CsA was added later than 48 hours after stimulation. Cell cycle analysis using propidium iodide as a DNA stain demonstrated that CsA prohibited the progression of B-CLL cells from the G1-phase to the S-phase of the cell cycle. However, we were also able to show that TNF-alpha induced proliferation of hairy cell leukemia (HCL) was not affected by CsA. This observation indicates that the inhibitory activity of CsA seems to be restricted to only a few haematological diseases such as B-CLL.