𝔖 Bobbio Scriptorium
✦   LIBER   ✦

Euratom innovation in nuclear fission: Community research in reactor systems and fuel cycles

✍ Scribed by G. Van Goethem; M. Hugon; V. Bhatnagar; P. Manolatos; M. Deffrennes


Publisher
Elsevier Science
Year
2007
Tongue
English
Weight
524 KB
Volume
237
Category
Article
ISSN
0029-5493

No coin nor oath required. For personal study only.

✦ Synopsis


The following questions are naturally at the heart of the current Euratom research and training framework programme:

(1) What are the challenges facing the European Union nuclear fission research community in the short (today), medium (2010) and long term (2040)? (2) What kind of research and technological development (RTD) does Euratom offer to respond to these challenges, in particular in the area of reactor systems and fuel cycles?

In the general debate about energy supply technologies there are challenges of both a scientific and technological (S/T) as well as an economic and political (E/P) nature. Though the Community research programme acts mainly on the former, there is nevertheless important links with Community policy. These not only exist in the specific area of nuclear policy, but also more generally as is depicted in the following figure. It is shown in the particular area of nuclear fission, to what extent Euratom research, education and innovation ("Knowledge Triangle" in above figure) respond to the following long-term criteria: (1) sustainability, (2) economics, (3) safety, and (4) proliferation resistance.

Research and innovation in nuclear fission technology has broad and extended geographical, disciplinary and time horizons:


πŸ“œ SIMILAR VOLUMES


Innovations in the ENHS reactor design a
✍ Ehud Greenspan; Ser Gi Hong; Ki Bog Lee; Lanfranco Monti; Tsuyoshi Okawa; Arnaud πŸ“‚ Article πŸ“… 2008 πŸ› Elsevier Science 🌐 English βš– 821 KB

A number of approaches were explored for improving characteristics of the encapsulated nuclear heat source (ENHS) reactor and its fuel cycle, including: increasing the ENHS module power, power density and the specific power, making the core design insensitive to the actinides composition variation w

Reactivity feedback and control margins
✍ Mohammad Javed Khan; Aslam; Nasir Ahmad πŸ“‚ Article πŸ“… 2006 πŸ› Elsevier Science 🌐 English βš– 226 KB

Three-dimensional neutronics analyses were performed to find the reactivity feedback coefficients and control margins under normal and presumed accidental conditions for the novel proliferation resistant, safer and economical natural uranium fueled and heavy water moderated nuclear research reactor

Burnup-dependent core neutronics analysi
✍ Siraj-ul-Islam Ahmad; Nasir Ahmad πŸ“‚ Article πŸ“… 2006 πŸ› Elsevier Science 🌐 English βš– 650 KB

The System for Analysis of Reactor Core (SARC) has been developed for burnup analysis of nuclear reactors using whole core modeling and simulation by coupling the WIMS-D4S and CITATION. The system has the capability to use 1981, 1986 and other WIMS-D libraries recently released by International Atom