Zobrazeno 1 - 10
of 5 654
pro vyhledávání: '"Gilbert Mark"'
Autor:
Stainer Thomas, Fleming Michael, Holcomb Andrew, Ogawa Tatsuhiko, Valtavirta Ville, Foster David, Bailey Greg, Gilbert Mark
Publikováno v:
EPJ Web of Conferences, Vol 302, p 07003 (2024)
The NEA Data Bank is an international reference centre for computer codes, nuclear and thermochemical data which has traditionally used simple file servers, and even DVDs, to deliver valuable content to end users across the globe. With the recent imp
Externí odkaz:
https://doaj.org/article/d37e3b0a1c474b50b3fd8252f4ec8376
Tungsten (W) is considered a leading candidate for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for magnetic and inertial fusion energy reactors are its high melting point, high therm
Externí odkaz:
http://arxiv.org/abs/2410.03998
Publikováno v:
EPJ Web of Conferences, Vol 247, p 18002 (2021)
For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design. A multi-step simulation process combining Monte Carlo Neutro
Externí odkaz:
https://doaj.org/article/4b50817a1e374ad7b2004c7da423b042
Autor:
Bradnam Steven C., Astromskas Vytautas, Ghani Zamir, Gilbert Mark R., Joyce Malcolm J., Packer Lee W.
Publikováno v:
EPJ Web of Conferences, Vol 247, p 16001 (2021)
The application and feasibility of a time-of-flight neutron detection system is explored for sources with time correlated gamma-ray and neutron emissions, such as the spontaneous fission emitter, Cf-252. For the emission of multiple gamma rays and ne
Externí odkaz:
https://doaj.org/article/5d1a9259cbec4c259ee4eb6715df122e
Autor:
Vilkhivskaya Olga, Gilbert Mark
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10015 (2021)
A reliable estimation of the operational parameters is one of the primary concerns in the design of magnetic fusion devices such as ITER and DEMO. Methods of diagnostics and control over the critical plasma parameters determining its stability and ef
Externí odkaz:
https://doaj.org/article/1a77b09b76e94a1c800c29a1db0533f8
Publikováno v:
EPJ Web of Conferences, Vol 247, p 09010 (2021)
An important area of research required for fusion reactor design is the study of materials under high energy neutron irradiation. Deuterium-Tritium (D-T) reactions release 14.1 MeV neutrons and material studies of such high energy neutrons focusing o
Externí odkaz:
https://doaj.org/article/5ae55acd269c4a6c8e3a7e0af014aa98