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Nowadays, the preservation of knowledge for the future generations is one of the problems in the world because the information is increasing fast as a result of the development of science and technology. In the case of the nuclear activity, the scientific and technological accumulated experiences should be preserved taking into consideration the new applications of the nuclear energy in different sectors of the human activity. For this, it is necessary to know the experts who work on different topics. This paper presents a performed study to obtain criterions from Cuban nuclear professionals about the conditions and principles to take into consideration for the selection of an expert in nuclear sciences and technologies. Appling Delphi method, it was obtained that years of experience, publications, participation in scientific events and scientific degree are more accepted criterions. [ABSTRACT FROM AUTHOR]

This paper is based on a gender analysis of the main scientific and technological activities carried out by specialists linked to nuclear applications in the nuclear sector and the Cuban nuclear science and technology program. All existing information regarding participation and leadership in science and innovation projects was collected, including projects implemented with the International Atomic Energy Agency, scientific publications, the Nuclear Energy and Advanced Technologies Agency (AENTA) Awards, Cuban Academy of Science Awards, National Innovation Awards, AENTA Branch Forum, international awards, state scientific-technological protection services - radiological surveillance and specialized productions. The analysis has been carried out for the period between 2000-2022, corresponding to the last 22 fiscal years in which there has been an increase in the active participation of women in the nuclear sphere, with the aim of contributing to the decisions in the design of policies and their implementation in the nuclear field for the empowerment of Cuban women in this sector, and with special contribution to the future actions of the Network of Cuban Women in the Nuclear, known as WiN Cuba. [ABSTRACT FROM AUTHOR]

Accelerator Mass Spectrometry (AMS) with 53Mn has geological applications as a chronometer for exposure and burial times for discontinuously deposited sediments. It has also been used to search for evidence of recent supernovae events, and proposed as a proxy to monitor the variation in the galactic cosmic ray spectrum over time. The current sensitivity limit amongst active facilities is 53Mn/ 55Mn = 3 × 1 0 − 13 while a sensitivity of 53Mn/ 55Mn = 1 × 1 0 − 13 is necessary to fully exploit 53Mn's capabilities. At the University of Notre Dame's Nuclear Science Laboratory (NSL), a 10 MV tandem accelerator and a Browne–Buechner Spectrograph operated as a gas-filled magnet were used to separate 53Mn from 53Cr. Samples covering ranges of 53Mn/ 55Mn = 1 0 − 10 − 1 0 − 8 were measured for the first time at the NSL using various settings resulting in a background level of 53Mn/ 55Mn = 6. 2 (3) × 1 0 − 11 . Analysis of the results, descriptions of experimental settings, and further explorations will be presented in this paper. [ABSTRACT FROM AUTHOR]

Nuclear Data Production System (NDPS), a fast neutron facility for nuclear science and applications, was constructed at the Rare Isotope Accelerator complex for ON-line experiments (RAON) in Korea. NDPS is designed to provide both white and quasi-monoenergetic neutrons using 98 MeV deuteron and 20 – 83 MeV proton beams with thick graphite and thin lithium targets, respectively. Neutron energy is determined by employing the Time-Of-Flight (TOF) technique, along with a pulsed deuteron (or proton) beam with a repetition rate of less than 200 kHz. Fast neutrons are produced in the target room and are guided to the TOF room through a 4 m long neutron collimator consisting of iron and 5% borated polyethylene. The neutron beam is monitored using a parallel plate avalanche counter (PPAC) and a micro-mesh gaseous (MICROMEGAS) detector installed in the TOF room, so as to measure the energy and the position of neutrons. [ABSTRACT FROM AUTHOR]

The Superallowed Transition Beta-Neutrino Decay Ion Coincidence Trap (St. Benedict) is currently under construction at the University of Notre Dame Nuclear Science Laboratory. It is designed to measure the beta-neutrino angular correlation parameter in superallowed mixed beta-decay transitions between mirror nuclei in order to extract the Fermi-to-Gamow Teller mixing ratio and test theoretical corrections entering in the determination of the V u d element of the Cabibbo–Kobayashi–Maskawa quark mixing matrix. St. Benedict includes a large volume gas catcher to thermalize the radioactive ion beam from TwinSol , a differentially-pumped extraction system, a radiofrequency quadrupole ion cooler and buncher, and a Paul trap for the observation and detection of the β decay products. The status of each of these components will be presented. [ABSTRACT FROM AUTHOR]

The Nuclear Physics European Collaboration Committee (NuPECC) has approved the Long Range Plan (LRP) 2024 for nuclear physics in Europe. The LRP serves as a framework for coordinated advances in nuclear science and provides national funding agencies, ESFRI, and the European Commission with priorities and opportunities for nuclear science in Europe. The LRP was developed through a bottom-up approach, with contributions from over 400 scientists, collaborations, research infrastructures, and institutions. The final version of the LRP will be published in the second half of 2024 and presented in Brussels on November 19, 2024. [Extracted from the article]

Thermal neutron scattering laws are important nuclear data for many nuclear science and engineering applications. Validation helps to ensure that a thermal neutron scattering law has a high quality and often employs critical benchmarks as integral experiments. Recently, pulsed-neutron die-away benchmarks have been used as an experiment to validate thermal neutron scattering laws. Herein, we evidence how this alternative integral experiment has a high sensitivity to these nuclear data by performing an uncertainty quantification analysis. The analysis randomly sampled the nuclear model parameters associated with hydrogen bound in light water thermal neutron scattering law and sampled other nuclear data that influenced the experiment's integral parameter (e.g., elastic scattering, absorption in hydrogen and oxygen) from their respective covariance matrices. The thermal neutron scattering law caused an uncertainty in the integral parameter that reached 2.67%, which exceeds by an order of magnitude the uncertainties induced in commonly used thermal solution critical benchmarks. The validation performed here, although limited due to a poor description of the historical experiment, indicated that the ENDF/B-VIII.0 thermal neutron scattering law well predicted the integral parameter. These results motivate further benchmark and validation efforts using pulsed-neutron die-away experiments. [ABSTRACT FROM AUTHOR]

Purpose: The purpose of this study is to measure the quality of nuclear science and technology research using the scientometric indicators, like activity index, attractivity index and publication efficiency index. Design/methodology/approach: The present scientometric study is based on the bibliographic data extracted from the core collection of the Web of Science database from 1989 to 2019. The data was collected using the advanced search feature, with a search string of 28 related terms. The bibliographic data for all the journal articles, excluding all other formats, was downloaded for statistical analysis. Findings: The present study highlights the growth pattern and the research efforts devoted to the field of nuclear science and technology worldwide, as reflected through the Core Collection of the Web of Science database, for 31 years from 1989 to 2019. The USA has emerged as the topmost producer, with a total share of almost 29% with respect to the world literature followed by Japan, Germany, France and UK. However, the relative citation impact has been the highest for Netherlands followed by the USA, Germany, France and UK, respectively. The study depicted that the activity index, also called as the relative performance indicator, has been the highest for the USA, whereas the attractivity index has been the highest for China, indicating its dominance in attracting citations to its publications in the field of nuclear science and technology. The publication efficiency index, the value has been the maximum for Iran, for which the value has been greater than 1 (1.618). The measure suggests that Iran's research effectiveness in the field of nuclear science and technology has been more than the research effort devoted to the field. Research limitations/implications: The paper was based on the data retrieved from a single database, and the results may vary across other databases. Hence, caution should be taken while generalizing the findings. Originality/value: Several scientometric studies have taken place in the field of nuclear science and technology, particularly in its allied branches, but none of the studies has focused on evaluating the research efforts carried out by the countries in terms of activity index, attractivity index and publication efficiency index, and the present study is an attempt to fill the gap. [ABSTRACT FROM AUTHOR]

Neutron-induced uranium fission reactions play an essential role in advanced nuclear energy research, basic and applied nuclear science. Based on the China Spallation Neutron Source (CSNS) Back-streaming white neutron source (Back-n), the measurement of the 236,238U fission cross sections relative to 235U from the threshold to 200 MeV was carried out by using time-of-flight (TOF) method with a multi-cell fast fission ionization chamber in double-bunch mode. The TOF spectra in double-bunch mode were unfolded by using Bayesian method. The fission cross section ratios of 238U/235U and 236U/235U were obtained. The experimental data of the 236,238U/235U fission cross section ratios measured in single-bunch mode were re-analyzed in high energy region and the upper limit was extended to 200 MeV for comparison. The experimental results in double-bunch mode are in good agreement with those in single-bunch mode and the main evaluation data within experimental uncertainties. The 236,238U(n,f) cross sections were obtained from the measured ratios and the standard 235U(n,f) cross sections and they agree well with the theoretical calculation, previous experiments, main evaluations and IAEA NDS. The experimental results can provide technical support for further experimental researches in double-bunch mode and relevant nuclear data evaluations. [ABSTRACT FROM AUTHOR]

41Ca (t 1/2 = 9.94 × 104 yrs) is an important stellar radionuclide and its production in the Early Solar System from various irradiation scenarios can help determine the viability of models of early stellar processes. A novel reaction technique has been under development and recently tested at the Nuclear Science Laboratory at the University of Notre Dame. This technique utilizes an "in-cathode" reaction method, where natural CaF 2 material is packed into an ion source sample holder (cathode) and then irradiated and subsequently measured using Accelerator Mass Spectrometry (AMS) without the need for chemical processing afterward. The setup for the irradiation was performed using a 3He beam to measure the reaction natCa(3He,x)41Ca. Initial AMS results suggest additional complexity due to ion source sputtering rates and geometry, which will need to be explored further. [ABSTRACT FROM AUTHOR]

Bangladesh Atomic Energy Commission TRIGA Research Reactor (BTRR) is a MK II type nuclear research reactor with a maximum thermal output power of 3 MW. Nuclear research/test reactors are designed for the development of nuclear science and technology including all necessary safety features. Safety issues are the prime concern for nuclear reactors to protect the nuclear accidents. BTRR has several passive and engineered safety features against any accidental failure of its control mechanisms leading to the meltdown of the reactor core or any other nuclear incident/accident. The nuclear percent power channel (NPP-1000) is one of the vital parts of the safety systems of the BTRR. Suddenly, the Instrumentation and Control (I&C) system of BTRR is tripped with a system SCRAM message "NPP HV Low". As a safety system, it is very compulsory to resolve the occurred uncertain issue before going to further reactor operation. To solve that kind of unwanted problem, effective troubleshooting steps were taken very carefully. Circuit analysis showed that a fault transistor was found inside the "HV trip circuit". By replacing this transistor with a good one, the corresponding relay is now functioning successfully and the "NPP HV low trip" condition as well as the "trip alarm" have been removed from the I&C system. Several types of experiments, research and training are now going on using this Bangladesh Atomic Energy Commission (BAEC) TRIGA Research Reactor facility by ensuring proper safety. Different troubleshooting experiences provide various strategies which are helpful for resolving many upcoming problems and also enrich the problem analyzing ability for further known or unknown tasks". [ABSTRACT FROM AUTHOR]

Inter-University Accelerator Centre (IUAC) came into existence as Nuclear Science Centre in 1984. A 15UD Pelletron accelerator was installed and it started delivering accelerated charged particle beams in 1991. Various experimental research facilities were set up in parallel at the Centre. All these facilities have been and are being extensively used by scholars and researchers from various universities and institutes in India. Research activities in nuclear physics, materials science and other inter-disciplinary fields are the main thrust at the laboratory. Nuclear physics research carried out at IUAC has made an indelible mark in the understanding of nuclear structure and nuclear reaction dynamics using heavy ion beams at near and above Coulomb barrier energy region. This review article presents the details of the various experimental facilities and highlights of research contributions in nuclear reactions and nuclear structure, spanning three decades. [ABSTRACT FROM AUTHOR]

As the scope of Accelerator Mass Spectrometry (AMS) expands, there is an increased need to extend the capability of isobaric separation to the medium-heavy mass region. Existing AMS facilities are limited in their ability to separate radioactive nuclei in the A = 100–200 range of interest from their neighboring stable isobars, as such measurements require higher energies than available in most facilities. ATLAS is one of the highest energy system used for AMS based experiments and has enabled isobaric discrimination for medium to heavy nuclides, notably via the Gas-Filled Magnet technique. A preparatory experiment performed in November, 2019, successfully demonstrated isobaric separation of 92Zr-92Mo using the Argonne Gas-Filled Analyzer (AGFA) with high magnetic rigidity. Since that time, MONICA, an eight-anode ionization chamber that measures both energy loss and position with two sets of split anodes, has been developed to aid in AMS experiments at AGFA and has undergone four commissioning runs at the Nuclear Science Laboratory at the University of Notre Dame utilizing Si, Fe/Ni, and Mn beams. This report presents the AGFA AMS run (November 2019) and the subsequent commissioning runs of the MONICA detector, including preliminary measurements on the long-lived isotopes 39Ar (268 y) and for the first time on 42Ar (33 y). [ABSTRACT FROM AUTHOR]

Neutron resonance cross sections are essential in many nuclear science fields and applications. However, their evaluation and application are extremely complicated. Additionally, the high-frequency, super-wide spectral range of these cross sections cannot be readily approximated by a deep neural network (DNN). To address this issue, we propose a single phase-shift DNN (SPDNN) in which a phase-shift layer is added to a conventional DNN before the output layer to enable wideband processing. Compared with multinetwork algorithms, SPDNN represents a more compact and efficient network, with far fewer parameters. The proposed SPDNN is used to learn the neutron resonance cross sections of 235U fission from the evaluated and experimental libraries, and the results demonstrate its capability as an easy-to-implement, efficient method for approximating the evaluated resonance cross sections and evaluating the experimental data. This study represents the first application of deep learning to the evaluation of highly complex neutron resonance cross sections by adapting DNN. [ABSTRACT FROM AUTHOR]

This experimental investigation focuses on the gamma-ray interaction parameters and the buildup factor in lanthanide compounds (CeO 2 , Ce(SO 4) 2 , Dy 2 (SO 4) 3 , C 3 O 9 Sm 2 , C 3 Gd 2 O 9 , Pr 2 O 3). These compounds were exposed to weak radioactive gamma sources with energies of 356, 511, 662, 1173, 1275, and 1332 keV by adopting narrow and broad beam geometry experimental arrangements. The incident and transmitted radiation intensities were measured using a NaI (Tl) detector. Experimentally measured values of mass attenuation coefficient and effective atomic number of lanthanide compounds were found to be in precise agreement with theoretical values obtained from NIST XCOM and Direct-Z eff database respectively. Additionally, the experimentally determined buildup factor values were compared with energy absorption buildup factor (EABF) and exposure buildup factor (EBF) values obtained from Phy-X/PSD software, providing insights into the gamma-ray penetration depth in terms of mean free path (MFP). At 356 keV, the EABF analysis showed that most compounds had a penetration depth of around 8 mean free paths. In contrast, the EBF analysis indicated penetration depths exceeding 10 mean free paths for all compounds except Ce (SO 4) 2. This new approach holds immense potential for transformative advancements in medical diagnostics, therapy, and the development of innovative technologies in nuclear sciences. • The gamma-ray interaction parameters and buildup factor of lanthanide compounds were experimentally determined. • The comparison of experimental buildup factor values with EABF and EBF provides insight into gamma-ray penetration depth (mfp). • The EABF showed that most compounds had a penetration depth of around 8 mean free path except Ce (SO 4) 2 at 356 keV. • The EBF indicated penetration depths exceeding 10 mean free path for all compounds except Ce (SO 4) 2 at 356 keV. [ABSTRACT FROM AUTHOR]

A custom Monte Carlo (MC) computer model was developed to simulate thermal neutron absorption in, and subsequent photon and electron emission from, natural Gd with a view to using the material as a neutron conversion layer for neutron detectors. The MC code also modelled photon and electron detection with two dissimilar detectors: a thick (500 μm) single crystal diamond detector; and a thin (5.15 μm) commercial off the shelf (COTS) 4H–SiC photodiode detector. The detectors' quantum detection efficiencies (QE) for hard X-rays and γ-rays were relatively low in comparison to their QE for electrons, thus making it possible to collect electron spectra from the Gd layer neutron conversion products which were not overwhelmed by photon emissions from the Gd. The MC code was utilised to determine the optimal thickness of Gd for the efficient detection of a thermal neutron flux. These radiation hard and spectroscopic detectors paired with natural Gd could find utility as robust and compact thermal neutron detectors for nuclear science and engineering, space science, and other applications. •Gd-Diamond and Gd-4H–SiC thermal neutron detectors modelled. • Optimum thickness of Gd converter layer found to be ≈ 0.7 μm. • Operation also possible with commercial-off-the-shelf Gd foils. • Rejection scheme to differentiate between photons and electrons not required. [ABSTRACT FROM AUTHOR]

[Display omitted] • This paper demonstrates the Kartini Reactor's educational utility. • A case study was conducted by investigating reactor criticality. • The study achieved reactor criticality by inserting 5 fuel elements, totaling 2524.57 g. • The critical mass determination was refined by plotting the inverse of counts against the total mass of U-235. • This approach utilized both polynomial and linear trend lines to analyze the data. Research reactors serve critical roles across multiple domains—from physics to medicine—while distinctly not being used for electrical power generation. The Kartini Research Reactor located in Indonesia exemplifies the integration of research reactors in education and scientific research, particularly highlighting its educational applications through the Internet Reactor Laboratory (IRL). Established in 1978 and operational since 1979, the Training Research and Isotope Production by General Atomic (TRIGA) Mark II reactor is instrumental in advancing nuclear science with facilities like the Lazy Suzan/Rotate Rack and Beam Port. The IRL significantly enhances its educational process, enabling remote access to reactor physics experiments, thus facilitating global university participation in nuclear engineering education. This capability allows for the real-time visualization of reactor operations and detailed presentation of operational data and experiment results, enriching the learning experience. This paper demonstrates the Kartini Reactor's educational utility through a case study investigating reactor criticality and determining the critical fuel mass under safe operational parameters. Employing telecommunication hardware and software, the study achieved reactor criticality by inserting 5 fuel elements, totaling 2524.57 g. The critical mass determination was further refined by plotting the inverse of counts against the total mass of U-235. This approach utilized both polynomial and linear trend lines to analyze the data. While the polynomial analysis provided upper and lower thresholds for critical mass, the linear regression offered a precise critical mass value of 2428.62 g, showcasing a deviation of only 4% from the experimental findings. [ABSTRACT FROM AUTHOR]

The document provides a calendar of upcoming short courses and workshops related to various scientific topics. Some of the events include the ATAS-AnXAS Joint Workshop on advanced techniques in actinide spectroscopy and radioactive materials, the JCNS Workshop on trends and perspectives in neutron scattering, the ANSTO-HZB Neutron Training Course, the MDANSE School on mastering materials through DFT & MD, the EMAS 2025 European Workshop on modern developments in microbeam analysis, the ECS 10 European Crystallography School, and the X-Ray Science conference. The events will take place in different locations around the world, including Germany, Australia, France, Spain, North Macedonia, and the United States. [Extracted from the article]

• Pioneering women in radiation science. • Women Role Models. • Highlighting women beyond Marie Sklodowska-Curie. • Challenges faced by pioneering women in radiation science. This review provides a concise historical summary of contributions from a selected group of pioneering women in radiation science born before the world war II – from the discovery of radioactivity through various scientific developments and breakthroughs. Starting from the renowned scientific contributions of Marie Sklodowska-Curie, we describe the work of numerous women pioneers whose discoveries propelled the field of radiation research. We also discuss the social and academic context in which this work emerged, highlighting their professional determination and excellence. While the scientific contributions of these women are invaluable for science in general, the importance of recognizing their work as an opportunity for developing role models for subsequent generations of women researchers is emphasized. [ABSTRACT FROM AUTHOR]

Ion beams from oxygen to uranium contribute to research for applications and fundamental nuclear science at a new DOE user facility. [ABSTRACT FROM AUTHOR]

Jeanne Tiehen's I The Theatre of Nuclear Science: Weapons, Power, and the Scientists behind it All i theoretically investigates theatrical representations of nuclear science. Writing during the pandemic, Tiehen connects nuclear weapons and their possible dangers to the overwhelming pandemonium, such as a lack of testing, vaccination hesitation, and the rejection of scientific expertise. Students and scholars of theatre, politics, and literature interested in the landscapes of nuclear science plays will find this an excellent book. [Extracted from the article]

The paper presents the concept and characteristics of nuclear security, the elements of the nuclear safety strategy, the legislative framework and the most important solutions from the Law on Radiation and Nuclear Safety and Security. At the international level, the most important entity in this field is the International Atomic Energy Agency, while at the national level, most important is the Directorate for Radiation and Nuclear Safety and Security of Serbia. An important role is played by the Vinca Institute of Nuclear Sciences as the most referential scientific institution in this field, as well as the operational bodies - Nuclear Facilities of Serbia, the Ministry of Internal Affairs, Ministry of Defence, and the Serbian Armed Forces. Engagement of these bodies is carried out in regular peacetime circumstances, emergency situations and wartime. The most important challenges, risks and threats to nuclear security of Serbia were pointed out as well as the need to harmonize norms, procedures and processes in purpose of the strengthening institutional mechanisms in the field of nuclear security. [ABSTRACT FROM AUTHOR]

The Training School was established to build research and development personnel for the Department of Atomic Energy (DAE) in a manner that does not drain away senior persons from the universities, but on the contrary, gives training, employment and opportunities to young graduates passing out of universities. Graduates of the Training School have made India fully competent in all aspects of nuclear science, technology and their applications, and have also contributed to several major scientific and technological efforts outside the ambit of atomic energy. Several educational programmes have been nurtured by the institutions set up by DAE and this has enabled the Department to set up the Homi Bhabha National Institute, a Deemed to be University, and further expand the educational programmes and intensify research and innovation through the medium of research students. [ABSTRACT FROM AUTHOR]

Chemistry is omnipresent in nuclear energy programmes all over the world. From the isolation and fabrication of fuel to the development of non-fuel materials and important nuclear processes, chemistry has played a crucial role. This article outlines the remarkable contribution that chemistry has made to the development of India's nuclear science programme. After a general introduction that deals with the inception and diversification of chemistry in the Department of Atomic Energy and some initial milestone achievements, a few notable contributions at BARC and IGCAR have been discussed in detail. These include the contribution of chemistry towards the front-end and back-end of the nuclear fuel cycle, nuclear safety, radiation chemistry and chemical innovations catering to the needs of society. Each subsection also includes possible future developments in the fields necessary for a sustainable nuclear energy programme. [ABSTRACT FROM AUTHOR]

The use of radiation and radioisotopes in human healthcare has been one of the early developments in the non-power applications of nuclear science. The field encompasses different facets of the use of radiation in the diagnosis and therapy of a wide variety of diseases, particularly cancer, the formidable challenge of the present century. There has been a significant advancement in different areas such as diagnostic radiology, diagnostic nuclear medicine, therapeutic radiation and therapeutic nuclear medicine, including theranostic applications in personalized medicine. The R&D efforts of the Department of Atomic Energy towards ensuring indigenous availability of established radiopharmaceuticals and treatment modalities as well as to develop emerging ones for state-of-the-art radiation-related services have been significant over the years. This article presents the current status, recent developments, clinical translation of developed products and prospects related to the use of radioisotopes and radiation in the two premiere research institutions of DAE, viz. BARC and TMC. [ABSTRACT FROM AUTHOR]

This article surveys the impact of Homi Bhabha's visionary initiatives in the area of electronics in India. We begin by surveying the early years at the Tata Institute of Fundamental Research, Mumbai and the Atomic Energy Establishment at Trombay that nucleated these activities and gave shape to Bhabha's conviction on the importance of electronics for the growth of science and technology and nuclear energy in the country. We trace the evolution of indigenous technology in the areas of nuclear electronics, instrumentation and control systems for nuclear power plants, and assess their impact. This is followed by a review of the role of the Electronics Corporation of India Ltd in the growth of indigenous electronics in the country. We conclude with an appraisal of the current state of electronics in India. [ABSTRACT FROM AUTHOR]

The world's first accelerator based epithermal neutron source for clinical boron neutron capture therapy (BNCT) was designed, developed, and commissioned between 2008 and 2010 by Sumitomo Heavy Industries in collaboration with Kyoto University at the Kyoto University Institute for Integrated Radiation and Nuclear Science. The accelerator system is cyclotron-based and accelerates a proton up to an energy of approximately 30 MeV. The proton strikes a beryllium target, which produces fast neutrons that traverse a beam shaping assembly composed of a combination of lead, iron, aluminum, and calcium fluoride to reduce the neutron energy down to the epithermal range (∼10 keV) suitable for BNCT. The system is designed to produce an epithermal neutron flux of up to 1.4 × 10 9 n · cm − 2 · s − 1 (exiting from the moderator of a 12 cm diameter collimator) with a proton current of 1 mA. In 2017, the same type of accelerator was installed at the Kansai BNCT Medical Center and in March 2020 the system received medical device approval in Japan (Sumitomo Heavy Industries, NeuCure® BNCT system). Soon after, BNCT for unresectable, locally advanced, and recurrent carcinoma of the head and neck region was approved by the Japanese government for reimbursement covered by the national health insurance system. [ABSTRACT FROM AUTHOR]

The National Center for Energy, Sciences and Nuclear Techniques (CNESTEN)’s Training Research and Isotope Production General Atomics (TRIGA) Mark II is a pool-type light water moderated and cooled research reactor operating at a maximum steady state thermal power of 2 MW. The reactor was designed to be used as a training facility for reactor operators, neutron activation analysis, isotopes production, and for implementing different reactor physics experiments. This article deals with the numerical and experimental characterization of reaction rates (RRs) in different irradiation channels inside the CNESTEN’s TRIGA Mark II research reactor, located in Rabat/Morocco. The main objective of this study is to validate the calculated neutron RRs against the measured ones and to prove that the new TRIPOLI-4 model of the reactor is capable to reproduce the measured quantities. Therefore, the measurements were carried out using the neutron activation technique and gamma spectrometry measurements. Preliminary simulations were performed with TRIPOLI-4 transport Monte Carlo code to establish the experimental design and set up for activation foils experiments. The selected set of foils with known characteristics were irradiated, at different power levels, inside the irradiation facilities of the TRIGA reactor. The resulting activities were evaluated via $\gamma $ spectrometry measurements. Normalized calculated and measured RRs were compared, and a good agreement was shown for most nuclides, which indicates that the new detailed TRIPOLI-4 model of the TRIGA reactor can accurately predict the relative experimental RRs values. Further work is ongoing to analyze absolute RR values, as well as to carry measurements in other irradiation channels. [ABSTRACT FROM AUTHOR]

Tritiated titanium targets were irradiated by the short-pulse OMEGA EP laser (1.25 kJ, 10 ps) to generate a laser-accelerated pulsed beam of tritons by target normal sheath acceleration. Using a Thomson parabola, the beam was found to contain 1012 tritons per pulse, with a mean energy of 2.2 MeV and an exponential tail reaching up to 10 MeV. In a separate experiment, the triton beam was directed onto a secondary deuterated polyethylene (CD) target to induce deuterium–tritium (D–T) nuclear reactions. Using neutron time-of-flight spectrometers, approximately 108 D–T fusion neutrons were observed per laser pulse. This triton beam presents new research opportunities for the study of the 3H(t, 2n)4He reaction and di-neutron transfers to lithium and beryllium that may produce exotic neutron-rich nuclei of interest to basic nuclear science, astrophysics, and inertial confinement fusion technology. [ABSTRACT FROM AUTHOR]

This article examines the struggle over the meaning of atomic science and nuclear power in mid-century French film culture, including popular and art cinema, newsreels, television, and industrial films produced by the French atomic energy commission. It considers the nuclear as a representational problem, rooted in the enduring iconicity of the bombings of Hiroshima and Nagasaki and the difficulty of making atomic science's value visible. Building on recent criticism of France's 'Trente glorieuses,' it focuses on the less-than-glorious image of nuclear power that filled French screens during the 1940s and 1950s, especially in two films released in 1950: René Clair's popular but largely forgotten, La beauté du diable, a Faust adaptation-cum-nuclear allegory, and Nicole Védrès's seldom-seen (but recently restored and re-released) La vie commence demain (the follow-up to her better-known Paris 1900 (1947)), which uses a who's who of French arts and letters—including Sartre, Gide, Prévert, Picasso, Le Corbusier and Jean Rostand, among others—to denounce nuclear weapons while imagining a future enlightened by peaceful atomic science. [ABSTRACT FROM AUTHOR]

On the occasion of the diamond jubilee of Radiochimica Acta (RCA), this article briefly describes the progress made by the journal during the last 10 years; a detailed account of the developments during the first 50 years having been given earlier (Radiochimica Acta 2012, 100, 483–492). Publishing responsibility for the journal was taken over in 2014 by Walter De Gruyter, a traditional German publishing company founded in 1749. This allowed RCA also to maintain its established traditional standard of publishing. Being broad-based, the journal encompasses all chemical aspects of nuclear science and technology. It has kept pace with the changing trends in radiochemical research. Today, besides fundamental nuclear chemistry, applied topics, such as chemical behaviour and mobility of actinides and fission products, accelerator-based radiochemistry, development of novel radiochemical techniques, study of radiation chemical effects, etc., are well represented. The journal is supported by a group of international Editors and Advisors who are distinguished radiochemists themselves. It follows a strict peer-review system and is assisted by a network of about 500 referees. About 200 manuscripts are received per year, out of which 40–45% are rejected. The impact factor (IF) of RCA is comparable to those of other radiochemistry-related journals, but the cited half-life (CHL) of RCA is by far the highest of all related journals. A list of top highly cited 100 articles has been provided alongside this article. In the past, most of the articles originated from Europe and North America, but in recent years the number of contributions from China and several developing countries has been increasing. All articles are published in English, and the journal is presently available to read both online and in a printed format. [ABSTRACT FROM AUTHOR]

Many scientists who are members of the Japan Society of Nuclear and Radiochemical Sciences have been involved in academic activities in response to the Fukushima Daiichi Nuclear Power Plant accident. Projects had been implemented that include determining radionuclides in environmental samples, identifying the distribution of radionuclides by large-scale soil monitoring, tracing radionuclide discharge time series, clarifying environmental dynamics of radionuclides, etc. For the last 10 years, these results have been shared and discussed in annual workshops partly sponsored by the society. This review summarizes the studies yielding these results, and they include reconstruction of the 131I distribution on soil by long-lived 129I analysis, reconstruction of the radioactive plume transport, identification of biological resuspension sources, discovery and characterization of cesium particles, and parameterization of the environmental behavior of radiocesium for dose assessment. [ABSTRACT FROM AUTHOR]

The Kindai University Reactor, UTR-KINKI, is a research reactor with a rated thermal power of 1 W. The reactor is designed especially for education and training at universities and has been utilized for the education and training of nuclear engineering students in Japan since its first criticality in 1961. It is also used to educate the general public about nuclear science and technology, such as in training workshops for science teachers and high school students. Recently, it has been used to train nuclear engineers from overseas. Under the framework of allowing researchers from all over Japan to use the reactor, researches are conducted such as detector testing, reactor physics experiments, biological irradiations, and so on. [ABSTRACT FROM AUTHOR]