JENDL: Nuclear databases for science and technology

Shibata, Kozo

doi:10.1080/00223131.2013.785282

Cited by 10 publications

(5 citation statements)

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“…Such data, organized and managed by the international nuclear science community, encompass an enormous energy range from 10 5 to 10 9 eV for hundreds of nuclides and thousands of radioisotopes. [144] The main reasons for furnishing new and better data are twofold: to validate theoretical calculations derived from analytical models and numerical simulations which in turn use the database, and to secure new experimental results and improved previous data that are needed to advance the field of nuclear physics and the technology of nuclear applications. Nuclear astrophysics is one of the important areas on the fundamental side.…”

Section: Nuclear Datamentioning

confidence: 99%

Research opportunities with compact accelerator-driven neutron sources

et al. 2016

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Since the discovery of the neutron in 1934 neutron beams have been used in a very broad range of applications, As an aging fleet of nuclear reactor sources is retired the use of compact accelerator-driven neutron sources (CANS) are becoming more prevalent. CANS are playing a significant and expanding role in research and development in science and engineering, as well as in education and training. In the realm of multidisciplinary applications, CANS offer opportunities over a wide range of technical utilization, from interrogation of civil structures to medical therapy to cultural heritage study. This paper aims to provide the first comprehensive overview of the history, current status of operation, and ongoing development of CANS worldwide. The basic physics and engineering regarding neutron production by accelerators, target-moderator systems, and beam line instrumentation are introduced, followed by an extensive discussion of various evolving applications currently exploited at CANS.

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Section: Nuclear Datamentioning

confidence: 99%

Research opportunities with compact accelerator-driven neutron sources

et al. 2016

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“…This study focused on conducting a neutronic analysis to determine the reactor core and fuel cell levels. The reactor core level was calculated using the multigroup diffusion equation approach and the fuel cell level was through the burnup equation on the SRAC program package version 2006 [8] with the JENDL 4.0 library [9]. The parameters evaluated include the burnup level, infinite (kinf) and effective (keff) multiplication factors, conversion ratio, atomic density, and power distribution.…”

Section: Introductionmentioning

confidence: 99%

The Effect of Burnable Poison Np-237 on the Conceptual Design of the GFR-2400 MWt Using MCANDLE Burnup Strategy

Monado,

Berliani,

Supardi

et al. 2024

Positron

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This study was used to design the Gas-cooled Fast Reactor (GFR) with 2400 MWt power as well as to implement a modified CANDLE (MCANDLE) burning strategy. Metallic uranium with Neptunium-237 at a concentration of 1% to 10% was used as burnable poison in the fuel while helium was applied as a coolant. Neptunium has been produced in conventional reactors by the decay product of plutonium obtained from U-238. This isotope has a relatively high absorption cross-section. As a nuclear waste, it is very useful to utilize as a burnable poison to reduce waste in the future and extend reactor operation lifetime with negligible reactivity. Moreover, the reactor was designed to operate for 100 years of burnup. Nuclear Fuel cell level calculations were conducted using the PIJ module and the reactor core was analyzed using the CITATION module contained in the SRAC. The core height was found to be 420 cm while the diameter was 300 cm and it was designed to have a refueling period of ten years. The survey parameters evaluated include burnup level, factor multiplication, conversion ratio, atomic density, and power distribution. The calculation conducted at the fuel cell level showed that the maximum value in the 76th year for the infinite multiplication factor was 1.30097. It was also discovered that the reactor core for the effective multiplication factor parameter with a fuel fraction of 55% was 1.094 without the addition of burnable poison.

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“…On the other hand, in the JENDL project, many special-purpose files have been developed to meet needs of various applications so far. 2 They cover not only neutron induced reactions but also charged particles and photon induced reactions. Regarding the neutron induced reaction files, two special-purpose files of JENDL/AD-2017 3 and JENDL/ImPACT-2018 4 were recently released to nuclear backend applications of activation evaluation for nuclear facilities and system development on nuclear transmutations of high-level radioactive wastes of long-lived fission products, respectively.…”

Section: Introductionmentioning

confidence: 99%

“…JENDL-5 was developed with targeting a revision of the general-purpose file and an integration of the special-purpose files. JENDL-5 was released in 2021, 8 consisting of 11 sublibraries; (1) neutron reaction, (2) thermal neutron scattering law, (3) fission product yield,…”

Section: Introductionmentioning

confidence: 99%