Obninsk Institute for Nuclear Power Engineering

For the generation of evaluated nuclear data sets required for the International Fusion Materials Irradiation Facility project, the basic features of the deuteron-lithium and neutron-lithium nuclear interactions are examined. Factors complicating the evaluation of deuteron-lithium reaction characteristics and weak points of previous calculations and evaluations are discussed. A new method to obtain double differential cross sections of particles emitted in d+Li reactions is described. The method is based on the diffraction approach, a modified intranuclear cascade model, and the usual evaluation techniques. The cross sections predicted by this method are in good agreement with existing experimental data for deuteron interactions in thick lithium targets. The study of neutron-lithium interactions is performed on the basis of different approaches: coupled channels, diffraction scattering, and direct breakup models.

For the first time, the data have been obtained on the effects of high-intensity terahertz (THz) radiation (with the intensity of 30 GW/cm 2 , electric field strength of 3.5 MV/cm) on human skin fibroblasts. A quantitative estimation of the number of histone Н2АХ foci of phosphorylation was performed. The number of foci per cell was studied depending on the irradiation time, as well as on the THz pulse energy. The performed studies have shown that the appearance of the foci is not related to either the oxidative stress (the cells preserve their morphology, cytoskeleton structure, and the reactive oxygen species content does not exceed the control values), or the thermal effect of THz radiation. The prolonged irradiation of fibroblasts also did not result in a decrease of their proliferative index.

cartilage formation. Extrusion-based bioprinting was used for the biofabrication. The printing parameters were tuned to obtain stable material flow. In vivo data proved the ability of the tested bioink to form a cartilage within five to six weeks after the subcutaneous scaffold implantation. Certain areas of cartilage formation were detected as early as in one week. The resulting cartilage tissue had a distinctive structure with groups of isogenic cells as well as a high content of glycosaminoglycans and type II collagen.

Analysis of the radiological burden of the spallation products (SP) was performed for various spallation targets (lead, tungsten, tin). The radiological burden was discussed in terms of toxicity based upon the concept of Annual Limit on Intake (ALI) shows that alpha-emitting rare earths (146Sm, 148Gd, 150Gd, 154Dy) are dominant. Their toxicity was estimated at equilibrium state with and without their transmutation. It is concluded that, in terms of toxicity, accumulation of SP in the target is quite comparable with transmutation of fission products (FP) in the blanket of Accelerator-Driven System (ADS).

The mechanism of the phase separation of a poly(ester sulfone) solution induced by water vapor and further immersion in water is studied via the methods of electron microscopy and porometry. The effect of the one-side treatment of the solution resting on a support with water on the porous structure of the formed membrane is investigated. Exposure to water vapor sufficient for penetration across the entire thickness leads to formation of a membrane with a gradient porous structure and a selective layer at the side contacting water vapor. With an increase in the rate of water sorption in the interval from 70 to 550 g/(m2 h), the average pore size in the selective layer decrease from 170 to 70 nm. When a solution is treated with water vapor not through the entire thickness, a selective layer is formed inside the membrane. In this case, when the duration of treatment with water vapor decreases, the internal selective layer is shifted toward the side contacting water vapor. During instantaneous immersion in water, the selective layer is formed at the side contacting water and its pores are 20–30 nm in size.

The convergent close-coupling method widely used now for calculations of charged particles scattering amplitudes is considered from the point of view of the rigorous many-body Coulomb scattering theory. It is shown that an approximate scattering amplitude calculated within the frame of the method does not converge to a solution of the corresponding Lippmann-Schwinger equation.

³ÑAEÇÓÉÂÐËÇ 1. £ÄÇAEÇÐËÇ (89).2. µÓÂÄÐÇÐËâ AEÎâ ×ÂÊÑÄÞØ ÒÑÄÇÓØÐÑÔÕÇÌ.®ÇÕÑAE ÔÕÂÙËÑÐÂÓÐÑÌ ×ÂÊÞ (90).3. ®ÇÕÑAE ÅÂÏËÎßÕÑÐÑÄÞØ ÖÓÂÄÐÇÐËÌ (92).4. ¤ÓÂÄËÕÂÙËÑÐÐÑ-ÍÂÒËÎÎâÓÐÞÇ ÄÑÎÐÞ Ð ÒÑÄÇÓØÐÑÔÕË ÉËAEÍÑÔÕË (93). 5. £ÑÎÐÑÄÑÌ ÔÎÇAE Ê AEÄËÉÖÜËÏÔâ ÖÓÂÅÂÐÑÏ (94).6. ±ÑAEÄÇÕÓÇÐÐÞÇ ÄÑÎÐÞ (95).7. °ÃÕÇÍÂÐËÇ Ä ÑÕÔÖÕÔÕÄËÇ ×ÑÐÑÄÑÅÑ ÄÓÂÜÇÐËâ (97).8. ¡ÔËÏÏÇÕÓËâ ÄÑÎÐÑÄÑÅÑ ÔÎÇAE Ê ÖÓÂÅÂÐÑÏ Ä ÒÓËÔÖÕÔÕÄËË b-à××ÇÍÕ (98).9. ©ÂÍÎáÚÇÐËÇ (99).10. ±ÓËÎÑÉÇÐËÇ (100).³ÒËÔÑÍ ÎËÕÇÓÂÕÖÓÞ (100).1. £ÄÇAEÇÐËÇ ²ÂÔÒÓÑÔÕÓÂÐÇÐËÇ AEËÔÒÇÓÅËÓÖáÜËØ ÄÑÎÐ Ä ÔÒÎÑÛÐÞØ ÔÓÇAEÂØ ËÏÇÇÕ ÑÔÑÃÇÐÐÑÔÕË, ÔÄâÊÂÐÐÞÇ Ô ÊÂÄËÔËÏÑÔÕßá ÔÍÑÓÑÔÕË ÓÂÔÒÓÑÔÕÓÂÐÇÐËâ ÑÕ AEÎËÐÞ ÄÑÎÐÞ.´ÂÍ, ÇÔÎË Ä ÕÂÍÑÌ ÔÓÇAEÇ ÓÂÄÐÑÏÇÓÐÑ ÒÇÓÇÏÇÜÂÇÕÔâ ÐÇÍÑÕÑÓÞÌ ËÔÕÑÚ-ÐËÍ ÄÑÊÏÖÜÇÐËâ, ÕÑ ÑÐ ÔÑÊAEÂÈÕ ÄÑÍÓÖÅ ÔÇÃâ ÄÑÎÐÑÄÖá ÍÂÓÕËÐÖ, ÑÔÐÑÄÐÞÏË ÑÔÑÃÇÐÐÑÔÕâÏË ÍÑÕÑÓÑÌ âÄÎâáÕÔâ ÒÑÄÇÓØÐÑÔÕË (ËÎË ÎËÐËË ì Ä AEÄÖÏÇÓÐÑÏ ÔÎÖÚÂÇ) ÒÑÔÕÑâÐ-ÐÑÌ ×ÂÊÞ.³ÕÓÖÍÕÖÓ àÕÑÌ ÍÂÓÕËÐÞ Ð ÓÂÔÔÕÑâÐËâØ, ÏÐÑÅÑ Ão ÎßÛËØ ÓÂÊÏÇÓÑÄ ËÔÕÑÚÐËÍÂ, ÒÓÂÍÕËÚÇÔÍË ÐÇ ÊÂÄËÔËÕ ÑÕ ÇÅÑ ×ÑÓÏÞ Ë ÑÒÓÇAEÇÎâÇÕÔâ Ä ÑÔÐÑÄÐÑÏ ÊÂ-ÍÑÐÑÏ AEËÔÒÇÓÔËË Ë ÔÍÑÓÑÔÕßá ÒÇÓÇÏÇÜÇÐËâ ËÔÕÑÚÐËÍÂ.•ÑÓÑÛÑ ËÊÄÇÔÕÐÞÌ ÒÓËÏÇÓ ÄÑÎÐÑÄÑÌ ÍÂÓÕËÐÞ AEÂÈÕ ÔËÔÕÇÏ ÍÑÓÂÃÇÎßÐÞØ ÄÑÎÐ, ÑÃÓÂÊÖáÜÂâÔâ ÒÓË AEÄËÉÇ-ÐËË ËÔÕÑÚÐËÍ ÒÑ ÒÑÄÇÓØÐÑÔÕË ÅÎÖÃÑÍÑÌ ÄÑAEÞ (ÓËÔ.1).¦ÜÈ ÑAEРâÓÍÂâ ÍÂÓÕËР(ÓËÔ.2, 3) ì ÔËÔÕÇÏ ÒÑAEÄÇÕÓÇÐ-ÐÞØ ÄÑÎÐ, ÄÑÊÐËÍÂáÜËØ Ä ÂÕÏÑÔ×ÇÓÇ ©ÇÏÎË ÒÓË ÑÃÕÇÍÂ-ÐËË ÒÑÕÑÍÑÏ ÑÓÑÅÓÂ×ËÚÇÔÍËØ ÐÇÑAEÐÑÓÑAEÐÑÔÕÇÌ (ËÊÑÎË-ÓÑÄÂÐÐÞØ ÅÑÓ, ÑÔÕÓÑÄÑÄ Ä ÑÍÇÂÐÇ).£ ×ÑÓÏËÓÑÄÂÐËË àÕÑÌ ÍÂÓÕËÐÞ ÖÚÂÔÕÄÖáÕ ËÐÇÓÙËÑÐÐÑ-ÅÓÂÄËÕÂÙËÑÐÐÞÇ ÄÑÎÐÞ (ª¤£), ÑÃÖÔÎÑÄÎÇÐÐÞÇ ÒÎÑÕÐÑÔÕÐÑÌ ÔÕÓÂÕË×ËÍÂÙËÇÌ ÂÕÏÑÔ×ÇÓÞ Ë ÇÈ ÄÓÂÜÇÐËÇÏ ÍÂÍ ÙÇÎÑÅÑ [1, 2].ÁÐÄÂÓß 2014 Å. ´ÑÏ 184, å 1 µ ³ ± ¦ • ª ¶ ª © ª ¹ ¦ ³ ¬ ª • ¯¡ µ ¬ ®¦´°¥ª¹¦³¬ª¦ ©¡®¦´¬ª ¶ÂÊÑÄÞÇ ÍÂÓÕËÐÞ AEËÔÒÇÓÅËÓÖáÜËØ ÄÑÎÐ ÑÕ AEÄËÉÖÜËØÔâ ÎÑÍÂÎËÊÑÄÂÐÐÞØ ËÔÕÑÚÐËÍÑÄ ±.¯.³ÄËÓÍÖÐÑÄ, ®.£.¬ÂÎÂÛÐËÍ ±ÓÇAEÎÑÉÇÐ ÑÃÜËÌ ÒÑAEØÑAE, ÒÑÊÄÑÎâáÜËÌ ÑÒËÔÞÄÂÕß ×ÂÊÑÄÖá ÔÕÓÖÍÕÖÓÖ ÄÑÎÐÑÄÞØ ÄÑÊÏÖÜÇÐËÌ

Boron is widely used in nuclear power as a neutron absorber material, thereby creating the possibility of controlling a nuclear reactor by changing the neutron multiplication factor. Natural boron contains about 20% 10B and 80% 11B with absorption sections respectively 3840 barn and 0.05 barn. The paper deals with changes in neutron-physical parameters of the reactor core of VVER type when the isotope content of 10B in boron carbide of absorber rods (AR) of the control and protection system (CPS) and in boric acid solution in the coolant of the VVER reactor is varied, and also analyzes the practicality of increasing the enrichment of 10B isotope in the control rods (CR). The model of VVER-1200 fuel assembly (FA) was used for calculations. In the course of work were modelled and the calculations of the three models of the coolant with different boric acid concentrations, as well as two models of AS with different enrichment in the isotope 10B.

The NJOY nuclear data processing system is a comprehensive computer code package for producing pointwise and multigroup cross sections and related quantities from evaluated nuclear data in the ENDF format, including the latest US library, ENDF/B-VI.The NJOY code can work with neutrons, photons, and charged particles, and it can produce libraries for a wide variety of particle transport and reactor analysis codes. INTRO1-1They are linked to one another by input and output files and a few common constants.NJOY directs the flow of data through the other modules and contains a library of common functions and subroutines used by the other modules.RECONR reconstructs pointwise (energy-dependent) cross sections from ENDF resonance parameters and interpolation schemes.BROADR Doppler-broadens and thins pointwise cross sections.UNRESR computes effective self-shielded pointwise cross sections in the unresolved energy range.HEATR generates pointwise heat production cross sections (KERMA factors) and radiation-damage-production cross sections.THERMR produces cross sections and energy-to-energy matrices for free or bound scatterers in the thermal energy range.GROUPR generates self-shielded multigroup cross sections, group-to-group scattering matrices, photon production matrices, and charged-particle cross sections from pointwise input.GAMINR calculates multigroup photoatomic cross sections, KERMA factors, and group-to-group photon scattering matrices.ERRORR computes multigroup covariance matrices from ENDF uncertainties.COVR reads the output of ERRORR and performs covariance plotting and output formatting operations.MODER converts ENDF "tapes" back and forth between formatted (that is, ASCII, EBCDIC, etc.) and blocked binary modes.DTFR formats multigroup data for transport codes that accept formats based on the DTF-IV code.CCCCR formats multigroup data for the CCCC standard interface files ISOTXS, BRKOXS, and DLAYXS.MATXSR formats multigroup data for the newer MATXS material cross-section interface file, which works with the TRANSX code to make libraries for many particle transport codes.RESXSR prepares pointwise cross sections in a CCCC-like form for thermal flux calculators.ACER prepares libraries in ACE format for the Los Alamos continuous-energy Monte Carlo code MCNP.POWR prepares libraries for the EPRI-CELL and EPRI-CPM codes.WIMSR prepares libraries for the thermal reactor assembly codes WIMS-D and WIMS-E.PLOTR makes plots of cross sections and perspective views of distributions for both pointwise and multigroup data. 1-2 INTRO"The DISSPLA plotting package is a product of ISSCO, Integrated Software Systems Corporation, 10505 Sorrento Valley Rd., San Diego, CA 92121. INTRO1-5 section) code.°TRANSX can produce libraries for a variety of particle transport codes, such as ANISN, 7 ONEDANT, 8 TWODANT, 9 and DIF3D. 10The MATXS format uses efficient packing techniques and flexible naming conventions that allow it to store all NJOY data types.A companion module, RESXSR, formats pointwise data into a CCCC-like format for use in thermal flux calculators.Pointwise data can also be fed directly into the ACER module.This module prepares cross sections and scattering laws in ACE format (A Compact ENDF) for the MCNP code.* All the cross sections are represented on a union grid for linear interpolation by taking advantage of the representation used in RECONR and BROADR."Laws" for describing scattering and photon production are very detailed, providing a faithful representation of the ENDF-format evaluation with few approximations.The data are organized for random access for purposes of efficiency.A future version of MCNP will be able to handle self-shielding in the unresolved-energy range using probability tables.The PURR module in this release of NJOY can be used to prepare these tables.Another alternate path for multigroup data is to use the POWR module to produce libraries for the power reactor codes EPRI-CELL or EPRI-CPM*.Similarly, the WIMSR module can be used to prepare libraries for the thermal reactor assembly codes WIMS-D and WIMS-E. 12 At the end of any NJOY run, the PLOTR module can be used to view the results or the original ENDF data.PLOTR can prepare 2-D plots with the normal combinations of linear and log axes, including legend blocks or curve tags, titles, and so on.Several curves can be compared on one plot (for example, pointwise data can be compared with multigroup results), and experimental data points with error bars can be superimposed, if desired.PLOTR can also produce 3-D perspective plots of ENDF and GENDF angle or energy distributions.The DISSPLA plotting system is required.The MIXR module can be used to combine isotopes into elements for plotting and other purposes.It only works for simple cross sections at the present time. C. Computer ImplementationNJOY is written in simple FORTRAN-77 with a few survivals from earlier times.As far as possible, features that are likely to be machine dependent (such as timers, date functions, and input/output) are isolated in special subroutines.Some Hollerith variables survive in places where they are appropriate, such as the 'EPRI-CELL and EPRI-CPM are proprietary products of the Electric

INTRODUCTION: The results of studies of clinical potential of a new domestic radiopharmaceutical 177 Lu-DOTA-PSMA in patients with metastatic castration-resistant prostate cancer are presented in this article. OBJECTIVE: The pharmacokinetics, safety and tolerability of radiopharmaceutical were studied. Tolerability of increasing activities — 5.0, 7.5 and 10.0 GBq was investigated. MATERIALS AND METHODS: The study included 12 patients with metastatic castration-resistant prostate cancer, who progressed after previous treatment. The first 4 patients was treated by 5 GBq of 177 Lu DOTA-PSMA, the next 4 patients of the second group was treated by 7.5 GBq, and the 4 patients of the third group was treated by 10 GBq. Radiopharmacokinetics was studied by whole-body scintigraphy, SPECT/CT, blood and urine radiometry. The radiation-absorbed dose (RAD) of metastases and organs at risk was studied by clinical dosimetry. Safety assessment also was studied by hematological status. All patients was taken a complete blood count, a biochemical blood test before course of therapy treatable and during the case study. RESULTS: Study data showed high accumulation of 177 Lu-DOTA-PSMA the in pathological focus, the distribution in the body conformed to the previous data of PET/CT study. Blood radiometry showed that 177 Lu-DOTA-PSMA rapidly excreted from the bloodstream (during the first hours after injection). Urine radiometry showed that, more than half of the injected dose was excreted during 2 days (from 34.4% to 88.8%). DISCUSSION: During the study was solicited increasing of pain syndrome, dry mouth. Most patients had moderate myelosuppression. Changes in hematological parameters had a transistor character, the adverse event resolved without consequences in 5 week. 4 th grade of NCI CTCAE hematological toxicity criteria wasn’t identified. Serious adverse events weren’t identified too. CONCLUSIONS: Radiopharmaceutical demonstrated high affinity for tumor tissue and safety in the clinical use. Data, which demonstrating a high potential anti-tumor efficacy of radiopharmaceutical, were obtained. Dosimetric studies showed radiation safety of work with radiopharmaceutical for the personnel.

И з в е с т и я в у з о в • Я д е р

The method of analyzing data known as Discrete Mathematical Analysis (DMA) incorporates fuzzy mathematics and logic. This paper focuses on applying DMA to study the morphology of time series by utilizing the language of fuzzy mathematics. The morphological characteristics of the time series, such as background, slopes, and vertices, are considered fuzzy sets within the domain of its definition. This allows for the use of fuzzy logic in examining the morphology of time series, ultimately leading to the detection of anomalies.

Passive autocatalytic recombiners (PARs) are essential safety systems used in nuclear power plants (NPPs) to prevent hydrogen explosions during severe accidents. This study investigates the operational behaviour of cylindrical-type catalysts used in a PAR. The study employs experimental and computational fluid dynamics (CFD) analyses to evaluate the catalyst temperature distribution and hydrogen conversion inside the PAR channel. Experimental analysis measures the hydrogen conversion of the catalyst and temperature distribution by means of hydrogen sensors and an infrared camera. The CFD analysis uses a three-dimensional (3D) model developed in STAR-CCM+ code to simulate the flow and recombination reaction in a cylindrical-type PAR catalyst section. Results indicated that the catalyst has decent conversion efficiency. Furthermore, the temperature over the catalyst section is evenly distributed and it does not exceed the lower hydrogen ignition limit. CFD analysis of the Schmidt number demonstrates that the flow inside the PAR is highly turbulent and Sct values is in the range of 0.2–0.28. It was found that the recombination reaction occurs in the diffusion regime. The recombination reaction primarily occurs in the catalyst's lower and central parts. Finally, this paper proposes the functional dependence to estimate the efficiency of the entire PAR based on the Sherwood equation and mechanistic transport approach. The results of this study provide crucial insight into the cylindrical-type catalyst operational behaviour in PARs and the CFD model design of cylindrical-type catalysts for the safety analysis of NPPs.

Abstract Currently, transuranic elements are a serious problem. They are formed in spent nuclear fuel as a result of the operation of reactors. These elements have a sufficiently high radioactivity and a huge half-life, thus they remain dangerous for a very long time and must be burned out on specialized reactors. However, not all of them can be classified exclusively as waste. Am-241, which has a low heat release due to its alpha decay, can be used as a radionuclide source for RTGs. However, this nuclide can maintain a fission chain reaction and emits gamma rays as a result of decay. The article investigates some properties of possible devices, as well as an assessment of the radiation protection for such devices.

Problems of efficient use of electric power and energy saving remain to be outstanding in our country. Implementation of smart systems for accounting and control of energy resources becomes the efficient solution of these problems. The problem of control and forecasting consumption of energy by the facility to cover internal needs represents an independent task. In general, systems are suggested which pertain to the control and accounting of energy resources supplied to the consumer of electric power. Approach to the development of system on the basis of concept of smart grids using dedicated complex of technical and software products allowing optimizing electric power expenditures, re-distributing electric power and promptly adjusting electric power grid characteristics is addressed in the present paper. Electric power supply control and monitoring devices receiving and transferring information to the server are installed in the places of connection of consumers to electric power supply grids. Server collects, accumulates and stores the information and is equipped with dedicated software allowing optimizing the load, preventing overloading and development of emergency situations within the electric power supply system. Such systems are suggested to be implemented by the facilities of nuclear industry.

Abstract Analysis of the radiological burden of the spallation products (SP) was performed for various spallation targets (lead, tungsten, tin). The radiological burden was discussed in terms of toxicity based upon the concept of Annual Limit on Intake (ALI) shows that alpha-emitting rare earths (146Sm, 148Gd, 150Gd, 154Dy) are dominant. Their toxicity was estimated at equilibrium state with and without their transmutation. It is concluded that, in terms of toxicity, accumulation of SP in the target is quite comparable with transmutation of fission products (FP) in the blanket of Accelerator-Driven System (ADS). KEYWORDS: spallation productstoxicityalpha-emitting rare earthsaccelerator-driven systemradiological burden

И з в е с т и я в у з о в •

Конвективная неустойчивость Рэлея в присутствии фазовых переходов влаги. Формирование крупномасштабных вихрей и облачных структур, Шмерлин Б.Я., Калашник М.В.

A library of cross-sections BISERM has been developed for the analysis of radiation damage sensitivity of nuclear power plant structural materials irradiated by nucleons of energies up to 800 MeV. The library contains information on neutron and proton displacement cross-sections, helium and hydrogen production cross-sections for 190 isotopes. The evaluation of the given cross-sections has been performed with a set of DIDACS/90 codes developed by the authors.

Radiation-induced changes of the structure and properties have been investigated for oxide and nitride materials, and the use of high-temperature insulators as temperature/dose monitors for in-reactor irradiation of materials test assemblies has been validated. It has been experimentally shown that the use of Al2O3 single crystals and BN ceramics provides means of monitoring the temperature of irradiation from 370 to 1900 K. The temperature is derived from measurements of the optical absorption or X-ray diffraction line shifts after post-radiation annealing of the monitors. We discuss the applicability of (a) the optical absorption and F-center luminescence spectroscopies of irradiated Al2O3 single crystals for gamma dose evaluation and (b) the isotopic analysis of irradiated BN ceramics for neutron dose evaluation.