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Journal articles on the topic 'Nuclear reaction codes'

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Published: 23 June 2021
Last updated: 29 July 2025

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1

Hilaire, Stéphane, Stéphane Goriely, and Sophie Péru. "Nuclear Level Densities." EPJ Web of Conferences 322 (2025): 06001. https://doi.org/10.1051/epjconf/202532206001.

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Nuclear reaction models, and in particular compound nucleus reactions, require the knowledge of nuclear level densities (NLDs), among other ingredients. For decades, analytical expressions have been used in nuclear reaction codes, due to the freedom they offer to the user to modify their associated parameters in order to fit cross sections. The development of computational resources has opened a new era, roughly 20 years ago, by allowing calculation of NLDs from more microscopic approaches and their use in reaction codes through tables stored in databases. During this 20 year period, several a
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2

Kataria, S. K., V. S. Ramamurthy, M. Blann, and T. T. Komoto. "Shell-dependent level densities in nuclear reaction codes." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 288, no. 2-3 (1990): 585–88. http://dx.doi.org/10.1016/0168-9002(90)90155-y.

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3

Cinan, Zehra Merve, Burcu Erol, Taylan Baskan, and Ahmet Hakan Yilmaz. "Heavy-Ion Fusion Reaction Calculations: Establishing the Theoretical Frameworks for 111In Radionuclide over the Coupled Channel Model." Energies 14, no. 24 (2021): 8594. http://dx.doi.org/10.3390/en14248594.

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In this work, the production of I111n radionuclide has been investigated theoretically via heavy-ion fusion reactions of two stable nuclei: C37l+G74e, M26g+R85b, S30i+B81r, and C46a+C65u reactions. Fusion cross-sections, barrier distributions, and potential energies on mutual orientations in the reactions planes of all reactions have been researched in detail around the barrier region via a coupled channel (CC) model using different codes. First of all, the most suitable codes and calculation parameter sets were determined through the C37l+G74e reaction, whose experimental data were available.
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Perkasa, Yuda S., Rizal Kurniadi, and Abdul Waris. "Application of TALYS code for Calculation of Fission Cross Section and Fission Yield of Several Heavy Nuclides." Indonesian Journal of Physics 20, no. 3 (2016): 49–53. http://dx.doi.org/10.5614/itb.ijp.2009.20.3.2.

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Nuclear data evaluation for fission cross section and fission yield had been performed by many investigators using different models of approximation theoretically. These models are encapsulated and implemented into computer codes to perform more robust nuclear reaction data calculations. TALYS is one of most successful nuclear reaction codes that used to determine fission cross section and fission yield. In this paper, TALYS code was used to calculate some fission reaction including Am-241 (n,f), Th-232 (n,f), and U-235 (n,f). These calculations are performed using different set of reaction me
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5

Garnaud, Louis, Luna Sobczak, Johann Piekar, et al. "Compendium on Monte Carlo simulation of photoneutrons in the Giant Dipole Resonance energy range: The first five elements." EPJ Web of Conferences 302 (2024): 07004. http://dx.doi.org/10.1051/epjconf/202430207004.

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Neutrons generated by photonuclear reactions, “photoneutrons”, are encountered in various applications involving high-energy gamma sources, electron accelerators or nuclear reactors. Monte Carlo particle-transport codes are generally used to simulate the emission of photoneutrons, characterize their field or assess their impact on nuclear systems. The aim of this work is to create a compendium on the simulation of photoneutrons using several Monte Carlo codes, i.e., MCNP6, PHITS and TRIPOLI-4, each code being run successively with ENDF/B-VIII.0 and JENDL-5 nuclear data libraries. We study the
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6

Gorbachenko, O. M., N. R. Dzysiuk, A. O. Kadenko, I. M. Kadenko, V. A. Plujko та G. I. Primenko. "Measurement and theoretical analysis of cross sections nuclear reaction (n, p), (n, α), (n, 2n) on isotopes of dysprosium, erbium and ytterbium". Nuclear Physics and Atomic Energy 13, № 2 (2012): 132–39. https://doi.org/10.15407/jnpae2012.02.132.

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Cross section of the nuclear reactions (n, p), (n, α), (n, 2n) were measured on isotopes of dysprosium, erbium and ytterbium at the neutron energies 14.6 ± 0.2 MeV. They were compared with available experimental data, evaluated nuclear data and the results of theoretical calculations. Cross sections were measured within neutron-activation method. Theoretical calculations of the nuclear cross sections reaction were performed with the use of EMPIRE 3.0 and TALYS 1.2 codes as well as by empirical and semi-empirical systematics.
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7

Kavun, Y., та R. Makwana. "Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes". Kerntechnik 86, № 6 (2021): 411–18. http://dx.doi.org/10.1515/kern-2021-1018.

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Abstract Oxygen and magnesium isotopes can be used in nuclear reactor materials as cooling, shielding, coating, electronics etc. They can also occur through nuclear reactions during the reactor operation. The exposure of high energy gamma can change the material and its properties, and hence its objective of selection may not remain satisfied. Thus, it is required to study the cross section of different reactions on nuclear reactor materials to understand their sustainability for the properties, for which they are chosen. In the scope of this study, theoretically, different level density model
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8

Beck, Bret, Caleb Mattoon, and Godfree Gert. "GIDI+: A GNDS 2.0 suite of C++ APIs to access nuclear and atomic data for use in radiation transport codes." EPJ Web of Conferences 284 (2023): 14004. http://dx.doi.org/10.1051/epjconf/202328414004.

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GIDI+ is a C++ package that reads GNDS formatted nuclear reaction and structure data, and photo-atomic reaction data as needed by radiation transport codes. As of version 3.25, GIDI+ supports reading GNDS 2.0 formatted data. GNDS is a new extensible hierarchy that has been internationally adopted as the new standard for storing nuclear and photo-atomic data, replacing ENDF-6 which has been the standard since the 1960’s. GIDI+ 3.25 supports the GNDS 2.0 map file which can contain a list of all GNDS data needed to make a complete nuclear reaction data library as needed by radiation transport cod
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9

Büyükuslu, Halim. "Deuteron Optical Model Calculations for Elastic and Inelastic Reactions on 14N, 16O, 27Al Target Nuclei." Journal of Advanced Applied Sciences 2, no. 2 (2023): 68–72. http://dx.doi.org/10.61326/jaasci.v2i2.112.

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Nuclear reaction cross sections have a key role in nuclear radioisotope production research. It is also an important part of applied fields such as energy production and experimental nuclear studies. It has been the subject of theoretical studies such as elucidating the nuclear structure and preparing and testing nuclear reaction models. It has become a very useful tool, especially for determining nuclear optical model parameters. In this study differential cross sections were calculated for elastic and inelastic scattering of 14-15 MeV energy range deuterons from 14N, 16O and 27Al. Calculatio
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10

Denikin, Andrey, Alexander Karpov, Mikhail Naumenko, Vladimir Rachkov, Viacheslav Samarin, and Vycheslav Saiko. "Synergy of Nuclear Data and Nuclear Theory Online." EPJ Web of Conferences 239 (2020): 03021. http://dx.doi.org/10.1051/epjconf/202023903021.

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The paper describes the NRV web knowledge base on low-energy nuclear physics developed in the Joint Institute for Nuclear Research. The NRV knowledge base working through the Internet integrates a large amount of digitized experimental data on the properties of nuclei and nuclear reaction cross sections with a wide range of computational programs for modeling of nuclear properties and nuclear dynamics. Today, the NRV becomes a powerful instrument for nuclear physics research as well as for educational applications. Advantages of the functioning scheme of the knowledge base provide the synergy
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11

Gorton, Oliver C., Calvin W. Johnson, and Jutta E. Escher. "A Problem in the Statistical Description of Beta-Delayed Neutron Emission." EPJ Web of Conferences 284 (2023): 03013. http://dx.doi.org/10.1051/epjconf/202328403013.

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Reaction measurements on fission products are being planned at both Argonne National Lab and at the Facility for Rare Isotope Beams. These indirect experiments produce specific short-lived nuclei via beta decay, and the subsequent neutron and gamma emission are studied. Some initial experiments found a surprising overabundance of gamma emission, which theory has yet to explain. To remedy this, we are developing an integrated nuclear data workflow that connects advanced nuclear shell model codes for describing the beta decay with a contemporary nuclear reaction model code.
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Henning, Greg, Antoine Bacquias, Catalin Borcea та ін. "MEASUREMENT OF 182,184,186W (N, N’ γ) CROSS SECTIONS AND WHAT WE CAN LEARN FROM IT". EPJ Web of Conferences 247 (2021): 09003. http://dx.doi.org/10.1051/epjconf/202124709003.

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Today’s development of nuclear installations rely on numerical simulation for which the main input are evaluated nuclear data. Inelastic neutron scattering (n, xn) is a reaction of importance because it modifies the neutron population, the neutron energy distribution and may create new isotopes. The study of this reaction on tungsten isotopes is interesting because it is a common structural material. Additionally, tungsten isotopes are a good testing field for theories. The IPHC group started an experimental program with the GRAPhEME setup installed at the neutron beam facility GELINA to measu
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Şekerci, Mert, Hasan Özdoğan та Abdullah Kaplan. "Level density model effects on the production cross-section calculations of some medical isotopes via (α, xn) reactions where x = 1–3". Modern Physics Letters A 35, № 24 (2020): 2050202. http://dx.doi.org/10.1142/s0217732320502028.

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Level density models have an undeniable importance for a better perception on the nature of nuclear reactions, which influences our life via various ways. Many novel and advanced medical application use radioisotopes, which are produced with nuclear reactions. By considering the connection between the level density models and the importance of theoretical calculations for the production routes of medically important isotopes, this study is performed to investigate the level density model effects on the production cross-section calculations of [Formula: see text]Zn, [Formula: see text]Ga, [Form
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14

Özdoğan, H., İsmail Hakki Sarpün, Mert Şekerci, and Abdullah Kaplan. "Production cross-section calculations of 111In via proton and alpha-induced nuclear reactions." Modern Physics Letters A 36, no. 08 (2021): 2150051. http://dx.doi.org/10.1142/s0217732321500516.

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[Formula: see text], a known gamma emitter, is used for many medical purposes such as imaging of myocardial metastases. It can be produced by using different nuclear reactions. In this study, the reactions of [Formula: see text]Ag([Formula: see text]2n)[Formula: see text], [Formula: see text](p,[Formula: see text]n)[Formula: see text], [Formula: see text](p,[Formula: see text]2n)[Formula: see text], [Formula: see text](p,[Formula: see text]3n)[Formula: see text] and [Formula: see text](p,[Formula: see text]4n)[Formula: see text], which are the production routes of [Formula: see text], were inv
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15

Zerkin, Viktor. "X4Pro – universal, fully relational EXFOR database." EPJ Web of Conferences 284 (2023): 14015. http://dx.doi.org/10.1051/epjconf/202328414015.

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EXFOR library contains experimental reaction data compiled by the Nuclear Reaction Data Centers (NRDC) since 1970 and presenting data from more than 25,000 experiments in the EXFOR format with associated dictionaries and documentation. The IAEA-NDS provides nuclear data services primarily through computer systems built on relational databases and retrieval software. X4Pro is an extended EXFOR relational database designed for programmatic access to whole EXFOR content and distributed as local SQLite database with demo-codes in Python and Fortran.
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16

Gandhi, A., Aman Sharma, Rebecca Pachuau та ін. "Measurement of (n,α) and (n,2n) reaction cross sections at a neutron energy of 14.92 ± 0.02 MeV for potassium and copper with uncertainty propagation *". Chinese Physics C 46, № 1 (2022): 014002. http://dx.doi.org/10.1088/1674-1137/ac2ed4.

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Abstract Experimentally measured neutron activation cross sections are presented for the (n,α) , (n,α) , and (n,2n) reactions with detailed uncertainty propagation. The neutron cross sections were measured at an incident energy of 14.92 ± 0.02 MeV, and the neutrons were based on the t(d,n)α fusion reaction. The (n,α) reaction was used as a reference reaction for the normalization of the neutron flux. The pre-calibrated lead-shielded HPGe detector was used to detect the residues' γ-ray spectra. The data from the measured cross sections are compared to the previously measured cross sections from
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17

Sarpün, İsmail Hakki, Hasan Özdoğan, Kemal Taşdöven, Hüseyin Ali Yalim, and Abdullah Kaplan. "Theoretical photoneutron cross-section calculations on Osmium isotopes by Talys and Empire codes." Modern Physics Letters A 34, no. 26 (2019): 1950210. http://dx.doi.org/10.1142/s0217732319502109.

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In this study, the level density parameter and the gamma ray strength function effects on photoneutron reaction cross-section calculations for Osmium isotopes were investigated by employing available level density models and gamma ray strength functions within Talys v1.8 and Empire v3.1 nuclear codes. A relative variance analysis was done to determine the best gamma ray strength function. Then, the effect of level density models for the photoneutron reactions was investigated by using the best gamma ray strength function. The results were compared with each other and also with the experimental
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18

Usman, Ahmed Rufai, and A. A. Ahmad. "EVALUATION OF 67Ga CROSS SECTIONS USING EXIFON CODE FOR MEDICAL APPLICATIONS." FUDMA JOURNAL OF SCIENCES 6, no. 3 (2022): 113–18. http://dx.doi.org/10.33003/fjs-2022-0603-987.

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Radioisotopes play very important roles in nuclear medicine for imaging and therapeutic applications. In the present studies, model calculation of excitation function for production of 67Ga radioisotope was performed using the EXIFON code, a nuclear reaction cross sections theoretical model code, for the reaction 65Cu(α, 2n)67Ga. The work was performed in the incident alpha energy range of 0 - 40 MeV. Similarly, the Q-value software (interface) was used for the calculation of reaction threshold and Q-value energies of the reaction of interest and were respectively found to be 14.97 MeV and -14
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19

Sakamoto, Koh. "RADIOCHEMICAL STUDY ON PHOTONUCLEAR REACTION MECHANISM AT INTERMEDIATE ENERGIES UPTO 1.2 GeV." Nucleus 47, no. 2 (2010): 67–89. https://doi.org/10.71330/thenucleus.2010.892.

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An account is given on radiochemical investigations on photonuclear reactions on target nuclei ranging from 7 Li to 209Bi at intermediate energies up to 1.2 GeV, with use of bremsstrahlung beams of its maximum end-point energies of E0 = 30–1200 MeV with small steps of E0, by the author's group since 1980s. The investigation covers the yield measurements of spallation, fragmentation, fission of the preactinides, 197Au and 209Bi, and photopion reactions, systematically performed with respect to photon energy (E0 and/or k) target mass (At) and/or target composition (N/Z)t, product mass (A) and
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20

Renzo, M., J. A. Goldberg, A. Grichener, O. Gottlieb, and M. Cantiello. "Progenitor Stars Calculated with Small Reaction Networks should not be Used as Initial Conditions for Core Collapse." Research Notes of the AAS 8, no. 6 (2024): 152. http://dx.doi.org/10.3847/2515-5172/ad530e.

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Abstract Core collapse initial conditions are a bottleneck in understanding the explosion mechanism(s) of massive stars. Stellar evolution codes struggle after carbon burning, and either stop or adopt numerical simplifications missing crucial physics. The use of small nuclear reaction networks (NRN) that account for energy production but bypass weak reactions is typical, but insufficient to study the dynamics of the collapse. We advise against the use of progenitors computed with small NRN in expensive multidimensional simulations of core collapse, bounce, (jet formation), and explosion.
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Hilaire, Stephane, Eric Bauge, Pierre Chau Huu-Tai, et al. "Potential sources of uncertainties in nuclear reaction modeling." EPJ Nuclear Sciences & Technologies 4 (2018): 16. http://dx.doi.org/10.1051/epjn/2018014.

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Nowadays, reliance on nuclear models to interpolate or extrapolate between experimental data points is very common, for nuclear data evaluation. It is also well known that the knowledge of nuclear reaction mechanisms is at best approximate, and that their modeling relies on many parameters which do not have a precise physical meaning outside of their specific implementations in nuclear model codes: they carry both specific physical information, and effective information that is related to the deficiencies of the model itself. Therefore, to improve the uncertainties associated with evaluated nu
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Moryakov, A., A. Zinchenko, V. Tsibulskiy, V. Davidenko, and B. Chukbar. "ESTIMATION OF REPRODUCTION FISSION ISOTOPES FOR NUCLEAR REACTOR IN BLANKET THERMONUCLEAR REACTOR." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, no. 2 (2019): 38–48. http://dx.doi.org/10.55176/2414-1038-2019-2-38-48.

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Calculations for the fusion reactor were carried. The purpose this one is assessment of an opportunity to use blanket of these units for fission isotopes reproduction for fission reactors. This paper contains: - full scale 3D model, where 1/8 space part was used (symmetry), biological shielding and toroidal coil winding were included in model, model size about 5,8 m for every X,Y,Z geometry axis; - results by MCU and LUCKY-A codes of neutron fluxes, reaction rates; - reproduction coefficient for thorium-232 as relation to intensity of neutron source; - analysis of results. MCU and LUCKY-A comp
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Smith, Alexander I., Eric T. Johnson, Zhi Chen, et al. "pynucastro: A Python Library for Nuclear Astrophysics." Astrophysical Journal 947, no. 2 (2023): 65. http://dx.doi.org/10.3847/1538-4357/acbaff.

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Abstract We describe pynucastro 2.0, an open-source library for interactively creating and exploring astrophysical nuclear reaction networks. We demonstrate new methods for approximating rates and use detailed balance to create reverse rates, show how to build networks and determine whether they are appropriate for a particular science application, and discuss the changes made to the library over the past few years. Finally, we demonstrate the validity of the networks produced and share how we use pynucastro networks in simulation codes.
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Korbut, Tamara, Maksim Kravchenko, Ivan Edchik, and Sergey Korneev. "Yalina-thermal facility neutron characteristic computational study 129I, 237Np and 243Am transmutation reaction rates calculations." EPJ Web of Conferences 239 (2020): 22013. http://dx.doi.org/10.1051/epjconf/202023922013.

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Present work describes Monte-Carlo calculations of the neutron field and minor actinide transmutation reaction rates within the Yalina-Thermal sub-critical assembly of the Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus. The computer model of the facility was prepared for the corresponding calculations via MCU-PD and MCNP Monte-Carlo codes. The model neutron characteristics estimations were performed as well as the nuclear safety analysis. The up-to-date ENDF B/VIII, JEFF 3.3 and JENDL 4.0 nuclear data libraries were used during research.
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Yiğit, M., and M. E. Korkmaz. "On the behavior of cross-sections of charged particle-induced reactions of 181Ta target." Modern Physics Letters A 33, no. 26 (2018): 1850155. http://dx.doi.org/10.1142/s0217732318501559.

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The production of nuclear energy from fusion reaction with no CO2 emission is one of the most attractive sources for the future. The unprecedented physical and mechanical properties for structural materials are very important in the nuclear fusion reactor design. So, tantalum material is a valuable candidate for plasma-facing materials in the fusion devices. In this paper, nuclear excitation functions for the [Formula: see text], [Formula: see text], [Formula: see text], [Formula: see text], [Formula: see text] and [Formula: see text] reactions are obtained using the nuclear codes TALYS 1.8 an
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Sabra, M. S., Robert A. Weller, Marcus H. Mendenhall, Robert A. Reed, Michael A. Clemens, and A. F. Barghouty. "Validation of Nuclear Reaction Codes for Proton-Induced Radiation Effects: The Case for CEM03." IEEE Transactions on Nuclear Science 58, no. 6 (2011): 3134–38. http://dx.doi.org/10.1109/tns.2011.2169989.

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Enferadi, Milad, and Mahdi Sadeghi. "122Sb - a potential radiotracer: Evaluation of cyclotron production via novel routes." Nuclear Technology and Radiation Protection 26, no. 1 (2011): 58–63. http://dx.doi.org/10.2298/ntrp1101058s.

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Antimony-122, having a half-life of 2.723 d and I?-=97.59%, is an important radiotracer in studies of environmental contamination and food crops. For the work discussed in this paper, the production of 122Sb was done via the natSn(p, xn)122Sb nuclear reaction. Radiochemical separation was performed by silica gel column chromatography and liquid-liquid extraction methods. Excitation functions for the 122Sb radionuclide, via 122Sn(p, n)122Sb, natSn(p, xn)122Sb, 122Sn(d, 2n)122Sb, natSn(d, xn)122Sb, 124Sn(p, 3n)122Sb and 124Sn(d, 4n)122Sb reactions, were calculated by ALICE/91, ALICE/ASH, and TAL
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Bird, Robert F., Patrick Gillies, Michael R. Bareford, Andy Herdman, and Stephen Jarvis. "Performance Optimisation of Inertial Confinement Fusion Codes using Mini-applications." International Journal of High Performance Computing Applications 32, no. 4 (2016): 570–81. http://dx.doi.org/10.1177/1094342016670225.

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Despite the recent successes of nuclear energy researchers, the scientific community still remains some distance from being able to create controlled, self-sustaining fusion reactions. Inertial Confinement Fusion (ICF) techniques represent one possible option to surpass this barrier, with scientific simulation playing a leading role in guiding and supporting their development. The simulation of such techniques allows for safe and efficient investigation of laser design and pulse shaping, as well as providing insight into the reaction as a whole. The research presented here focuses on the simul
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Enferadi, Milad, Mahdi Sadeghi, and Fatemeh Bolourinovin. "Accelerator production and nuclear aspects of 88Y: An efficient radiotracer." Nuclear Technology and Radiation Protection 26, no. 3 (2011): 201–8. http://dx.doi.org/10.2298/ntrp1103201e.

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Yttrium-88 (T1/2 = 106.6 d, Ib+ = 0.2% and IEC = 99.8%) is used in mixed gamma efficiency calibration standards and also as a substitute for 90Y to quantify the biodistribution of Y-pharmaceuticals in animals. Yttrium-88 and strontium-85 as gamma emitting radiotracers were produced via natSrCO3(p, xn) and natRbCl(p, xn) nuclear processes at AMIRS, with 18 and 15 MeV protons, respectively, at a current of 20 ?A for 10 hours. The deposition of natSrCO3 on the Cu backing was carried out by means of the sedimentation method. Yt- trium-88 was separated in a 92 ? 5% radiochemical yield using the pre
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Chasapoglou, S., R. Vlastou, M. Diakaki, et al. "Investigation of (n,x) reactions on enriched Ge targets at 15.7 MeV at the upgraded facility of NCSR “Demokritos”." EPJ Web of Conferences 294 (2024): 01007. http://dx.doi.org/10.1051/epjconf/202429401007.

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Neutron induced reaction cross-section measurements display special interest both for fundamental research in the Nuclear Physics field and many practical applications. The Institute of Nuclear and Particle Physics (INP) of the National Centre for Scientific Research Demokritos (N.C.S.R. “D”) hosts the 5.5 MV T11/25 Van de Graaff accelerator, which is the only accelerator used in Greece for research purposes. This accelerator recently underwent a major upgrade, including the installation of a new pelletron charging system, two new ion sources, a new gas stripper and beam optics. This neutron f
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Chasapoglou, Sotirios, A. Tsantiri, A. Kalamara, et al. "Study of the 232Th(n,f) Cross section at NCSR ‘Demokritos’ using Micromegas Detectors." HNPS Proceedings 27 (April 17, 2020): 106. http://dx.doi.org/10.12681/hnps.2994.

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The accurate knowledge of neutron-induced fission cross sections in actinides, is of great importance when it comes to the design of fast nuclear reactors, as well as accelerator driven systems. Specifically for the 232Th(n,f) case, the existing experimental datasets are quite discrepant in both the low and high energy MeV regions, thus leading to poor evaluations, a fact that in turn implies the need for more accurate measurements.In the present work, the total cross section of the 232Th(n,f) reaction has been measured relative to the 235U(n,f) and 238U(n,f) ones, at incident energies of 7.2,
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Voinov, A. V., S. M. Grimes, C. R. Brune, et al. "Level Density Inputs in Nuclear Reaction Codes and the Role of the Spin Cutoff Parameter." Nuclear Data Sheets 119 (May 2014): 255–57. http://dx.doi.org/10.1016/j.nds.2014.08.070.

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Kerveno, Maëlle, Marc Dupuis, Catalin Borcea та ін. "What can we learn from (n,xnγ) cross sections about reaction mechanism and nuclear structure?" EPJ Web of Conferences 239 (2020): 01023. http://dx.doi.org/10.1051/epjconf/202023901023.

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Inelastic (n,n') cross section is a key quantity to accurately simulate reactor cores, and its precision was shown to need significant improvements. To bypass the experimental difficulties to detect neutrons from (n,xn) reaction and to discriminate inelastically scattered neutrons from those following the fission process in case of fissile targets, an indirect but yet powerful method is used: the prompt γ-ray spectroscopy. Along this line, our collaboration has developed the GRAPhEME setup, optimized for actinides, at the GELINA facility to measure partial (n,xn γ) cross sections, from which t
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Watanabe, Yukinobu, Hiroki Sadamatsu, Shouhei Araki, et al. "Study of the Li(d, xn) reaction for the development of accelerator-based neutron sources." EPJ Web of Conferences 239 (2020): 20012. http://dx.doi.org/10.1051/epjconf/202023920012.

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Double-differential neutron production cross sections (DDXs) for deuteron-induced reactions on Li at 200 MeV were measured for emission angles ranging from 0◦ to 25◦ in steps of 5◦ by means of a time of flight (TOF) method with EJ301 liquid organic scintillators at the Research Center for Nuclear Physics (RCNP), Osaka University. The measured DDXs were compared to theoretical model calculations with the DEURACS and PHITS codes and TENDL-2017 nuclear data. It was found that the DEURACS calculation is in better agreement with the measured DDXs than the PHITS calculation, while TENDL-2017 fails t
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Clark, Alexander Smith, Eric T. Johnson, Zhi Chen, et al. "pynucastro 2.1: an update on the development of a python library for nuclear astrophysics." Journal of Physics: Conference Series 2742, no. 1 (2024): 012003. http://dx.doi.org/10.1088/1742-6596/2742/1/012003.

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Abstract pynucastro1 is an open-source python library that provides visualization and analyze techniques to classify, construct, and evaluate nuclear reaction rates and networks. It provides tools that allow users to determine the importance of each rate in the network, based on a specified list of thermodynamic properties. Additionally, pynucastro can output a network in C++ or python for use in simulation codes, include the AMReX-Astrophysics simulation suite. We describe the changes in pynucastro since the last major release, including new capabilities that allow users to generate reduced n
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Nadeem, Muhammad, Syed Hameed Qaiser, Tayyab Mahmood, Atta Muhammad, and Muhammad Sajjad. "Cross-section Calculations of 175Lu(n,p)175Yb reaction for production of medically important radioisotope 175Yb." EPJ Web of Conferences 322 (2025): 09003. https://doi.org/10.1051/epjconf/202532209003.

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Ytterbium-175 (175Yb) is considered suitable for the preparation of therapeutic radiopharmaceuticals due to its decay characteristics (T1/2 = 4.18 d). In this study, the reaction cross section via the (n, p) reaction for 175Yb was theoretically calculated using Lutetium-175 (175Lu) as the target material. Neutrons with energies up to 50 MeV were considered, taking into account all nuclear reaction mechanisms. The Q-value for the neutron-induced reaction is 312 keV. The produced 175Yb can be converted back to the parent stable nuclei 175Lu through beta decay (100%), with no co -produced impurit
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Henning, Greg, Kerveno Maëlle, Philippe Dessagne та ін. "Measurement of 183W(n, n’γ) and (n, 2nγ) cross-sections (preliminary)". EPJ Web of Conferences 284 (2023): 01046. http://dx.doi.org/10.1051/epjconf/202328401046.

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The necessary improvement of evaluated nuclear databases for appplication will be achieved with improvement of models and new, precise data. In particular, the effect of inelastic neutrons scattering can be of importance for reactors. In order to test the models, we performed measurement of (n, n’γ) and (n, 2nγ) cross-sections on 183W. These data will help constrain the calculation codes and ensure a better evaluation of the total (n, xn) cross section. The experimental setup and the data analysis method will be presented. The preliminary experimental results for the 183W isotope will be compa
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38

Hedden, O. F. "Status of Code Cases Related to Application of Risk-Informed Inservice Inspection in ASME Code Section XI." Journal of Pressure Vessel Technology 120, no. 4 (1998): 438–40. http://dx.doi.org/10.1115/1.2842356.

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ASME Code Section XI Cases N-577 and N-578, for application of risk-informed technology to examination of piping systems in nuclear power plants, are proceeding, with review and acceptance by ASME Board on Nuclear Codes and Standards and by the U.S. Nuclear Regulatory Commission remaining before implementation. Sources of support for a favorable reaction by NRC will be reviewed, starting with developmental research sponsored by NRC in the late 1980s. Extensive discussion in the engineering community as exemplified by forums presented by ASME PVP in 1994 and 1995 will be cited. Recent academic
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GÜLÜMSER, Tuğçe, and Abdullah KAPLAN. "Cross-Section Calculations of Medical Radioisotope 64Cu via some Proton, Neutron and Deuteron Reactions." Cumhuriyet Science Journal 44, no. 3 (2023): 583–89. http://dx.doi.org/10.17776/csj.1290957.

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The Copper-64 radioisotope, whose academic research continues on diagnostic and therapeutic use, was examined in this study. 64Cu radioisotope is unique among other Cu isotopes for medical usage due to its low positron energy, appropriate half-life, and short tissue penetration. In cases where experimental data are missing, cross-section calculations can be used, and the existence of the cross-section data may provide various advantages in managing time, cost, and efficiency. In this context, investigated detailed cross-section calculations of the 64Cu isotope. To this end, cross-sections acqu
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De Saint Jean, Cyrille, Pierre Tamagno, Pascal Archier, and Gilles Noguere. "CONRAD – a code for nuclear data modeling and evaluation." EPJ Nuclear Sciences & Technologies 7 (2021): 10. http://dx.doi.org/10.1051/epjn/2021011.

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The CONRAD code is an object-oriented software tool developed at CEA since 2005. It aims at providing nuclear reaction model calculations, data assimilation procedures based on Bayesian inference and a proper framework to treat all uncertainties involved in the nuclear data evaluation process: experimental uncertainties (statistical and systematic) as well as model parameter uncertainties. This paper will present the status of CONRAD-V1 developments concerning the theoretical and evaluation aspects. Each development is illustrated with examples and calculations were validated by comparison wit
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Werneth, Charles M., K. M. Maung, M. D. Vera, and L. W. Townsend. "Optical potential for light nuclei and momentum-space eikonal phase function." Canadian Journal of Physics 96, no. 6 (2018): 642–49. http://dx.doi.org/10.1139/cjp-2017-0219.

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The space radiation environment comprises all of the nuclei in the periodic table with energies that extend from a fraction of an MeV/n to TeV/n. The vast range of projectile–target and energy combinations necessitates highly efficient and accurate cross section codes for use in radiation transport codes. As particles in the space radiation environment impinge on shielding materials, nuclear reactions, such as nuclear fragmentation, occur. One way of estimating nuclear fragmentation cross sections is to use an abrasion–ablation model, which describes how nucleons are dislodged from the nuclei
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Raj, Prasoon, Ulrich Fischer, Axel Klix, and JET Contributors. "Comparative survey of evaluated nuclear data libraries for fusion-relevant neutron activation spectrometry." EPJ Web of Conferences 239 (2020): 21003. http://dx.doi.org/10.1051/epjconf/202023921003.

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The neutron flux-spectrum in a fusion device is frequently determined with activation foils and adjustment of a guess-spectrum in unfolding codes. Spectral-adjustment being a rather complex and uncertain procedure, we are carefully streamlining and evaluating it for upcoming experiments. Input nuclear cross-section data holds a vital position in this. This paper presents a survey of common dosimetry reactions and available data files relevant for fusion applications. While the IRDFF v1.05 library is the recommended source, many reactions of our interest are found missing in this. We investigat
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Isazadeh, Farzad, та Akbar Abdi Saray. "Simulation of the indirect reaction 92Mo(α, 2n)94Ru→m94Tc using TALYS and GEANT4 nuclear codes". Applied Radiation and Isotopes 200 (жовтень 2023): 110959. http://dx.doi.org/10.1016/j.apradiso.2023.110959.

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Khaliel, A., T. J. Mertzimekis, A. Psaltis, et al. "Experimental Investigation of radiative proton-capture reactions relevant to Nucleosynthesis." HNPS Proceedings 24 (April 1, 2019): 168. http://dx.doi.org/10.12681/hnps.1861.

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One of the primary objectives of the field of Nuclear Astrophysics is the study of the elemental and isotopic abundances in our solar system. Although a lot of progress has been made regarding a large number of nuclides, there is still a number of neutron-deficient nuclei, ie the p nuclei, which cannot be created via the s and r processes. These processes are responsible for the production of the bulk of heavy nuclides. The pre-explosive or explosive phases of massive stars are considered potential loci for p nuclides production via various combinations of photodisintegrations and nucleon capt
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Al-Adili, A., A. Solders, and V. Rakopoulos. "Employing TALYS to deduce angular momentum rootmean-square values, Jrms, in fission fragments." EPJ Web of Conferences 239 (2020): 03019. http://dx.doi.org/10.1051/epjconf/202023903019.

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Fission fragments exhibit large angular momenta J, which constitutes a challenge for fission models to fully explain. Systematic measurements of isomeric yield ratios (IYR) are needed for basic nuclear reaction physics and nuclear applications, especially as a function of mass number and excitation energy. One goal is to improve the current understanding of the angular momentum generation and sharing in the fission process. To do so, one needs to improve the modeling of nuclear de-excitation. In this work, we have used the TALYS nuclear-reaction code to relax excited fission fragments and to e
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Yokoyama, Atsushi, Shogo Katsura, and Akira Sugawara. "Biochemical Analysis of Histone Succinylation." Biochemistry Research International 2017 (2017): 1–7. http://dx.doi.org/10.1155/2017/8529404.

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Posttranslational modification (PTM) of proteins is used to regulate protein activity and stability. Histone PTMs are regarded as some of the most important, as they can directly regulate gene expression through chromatin reorganization. Recently, histone proteins were found to undergo succinylation, adding to other well-known PTMs such as acetylation, methylation, and phosphorylation. However, there is little information regarding the enzyme which catalyzes histone lysine succinylation. In fact, it is unclear whether this reaction is enzymatic. In this study, we tested histone succinylation a
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Irkimbekov, Ruslan A., Aleksandr D. Vurim, Sergey V. Bedenko, Artur S. Surayev, and Galina A. Vityuk. "Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor." Nuclear Energy and Technology 8, no. (3) (2022): 167–72. https://doi.org/10.3897/nucet.8.93895.

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IVG.1M is a research pressurized water reactor designed to use high-enriched fuel. As part of the core conversion program, the reactor will be switched to a new low-enriched composite uranium fuel. Further operation of the reactor is determined by the availability of fresh fuel to replace the core after the next campaign and the possibility of ensuring safe storage of irradiated spent nuclear fuel (SNF) unloaded from the core. The SNF storage conditions are assessed in terms of ensuring nuclear and radiation safety. Radiation safety of the research reactor fuel storage is achieved, first of al
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48

Bahadir, Tamer. "BEAVRS BENCHMARK EVALUATION WITH CASMO5 AND SIMULATE5." EPJ Web of Conferences 247 (2021): 06022. http://dx.doi.org/10.1051/epjconf/202124706022.

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The MIT BEAVRS benchmark problem, which was primarily setup for the verification and validation of high-fidelity tools that have coupled neutron transport, thermal-hydraulics, and fuel isotopic depletion models, has also found extensive usage in the reactor physics community for validating core analysis tools. The primary purpose of this paper is to provide an accurate, comprehensive evaluation of the BEAVRS benchmark with CASMO5 and SIMULATE5 codes. The CMS5 calculated results for low-power physics tests (hot zero power critical boron, control rod worth and isothermal temperature coefficients
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Kerveno, Maëlle, Catalin Borcea, Marian Boromiza, et al. "GRAPhEME: Performances, achievements (@EC-JRC/GELINA) and future (@GANIL/SPIRAL2/NFS)." EPJ Web of Conferences 284 (2023): 01005. http://dx.doi.org/10.1051/epjconf/202328401005.

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GRAPhEME is a γ-spectrometer developed by CNRS/IPHC Strasbourg (France), in collaboration with EC-JRC Geel (Belgium) and IFIN-HH Bucharest (Romania). With its 6 High Purity Planar Germanium detectors and one fission chamber, GRAPhEME, installed at the EC-JRC GELINA facility, was optimized for measurements of accurate (n, xnγ) cross sections on actinides. The experimental methodology is based on the prompt γ-ray spectroscopy coupled to time-of-flight measurements. In this paper, we present an overview of fifteen years of experiments with GRAPhEME at EC-JRC GELINA facility, illustrated by main a
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Milocco, A., and A. Trkov. "Modelling of the Production of Source Neutrons from Low-Voltage Accelerated Deuterons on Titanium-Tritium Targets." Science and Technology of Nuclear Installations 2008 (2008): 1–7. http://dx.doi.org/10.1155/2008/340282.

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Fast quasi-monoenergetic neutrons can be produced by accelerating charged deuterons on tritium solid targets. Benchmark experiments were performed in many laboratories with intense D-T neutron sources. The aim is to validate the computational models and nuclear data for fusion applications. The detailed information on the neutron source term is highly important for the benchmark analyses. At present, the MCNP family of codes cannot explicitly model the D-T reaction for Deuterons in the KeV energy range. The physics for the D-T neutron production was modelled at ENEA (Italy) in the SOURCE and S
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