Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

HPRL; International cooperation to identify and monitor priority nuclear data needs for nuclear applications

Dupont, E.*; Bossant, M.*; Capote, R.*; Carlson, A. D.*; Danon, Y.*; Fleming, M.*; Ge, Z.*; Harada, Hideo; Iwamoto, Osamu; Iwamoto, Nobuyuki; et al.

EPJ Web of Conferences, 239, p.15005_1 - 15005_4, 2020/09

 Times Cited Count:0 Percentile:0.19

Journal Articles

Evaluation of large 3600 MWth sodium-cooled fast reactor OECD neutronic benchmarks

Buiron, L.*; Rimpault, G*; Fontaine, B.*; Kim, T. K.*; Stauff, N. E.*; Taiwo, T. A.*; Yamaji, Akifumi*; Gulliford, J.*; Fridmann, E.*; Pataki, I.*; et al.

Proceedings of International Conference on the Physics of Reactors; The Role of Reactor Physics toward a Sustainable Future (PHYSOR 2014) (CD-ROM), 16 Pages, 2014/09

Within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of the OECD, an international collaboration is ongoing on the neutronic analyses of several Generation-IV Sodium-cooled Fast Reactor (SFR) concepts. This paper summarizes the results obtained by participants from institutions of different countries (ANL, CEA, ENEA, HZDR, JAEA, CER, KIT, UIUC) for the large core numerical benchmarks. These results have been obtained using different calculation methods and analysis tools to estimate the core reactivity and isotopic composition evolution, neutronic feedbacks and power distribution. For the different core concepts analyzed, a satisfactory agreement was obtained between participants despite the different calculation schemes used. A good agreement was generally obtained when comparing compositions after burnup, the delayed neutron fraction, the Doppler coefficient, and the sodium void worth. However, some noticeable discrepancies between the k-effective values were observed and are explained in this paper. These are mostly due to the different neutronic libraries employed (JEFF3.1, ENDFB7.0 or JENDL-4.0) and to a lesser extent the calculations methods.

JAEA Reports

JNC-CEA GCFR core neutronic benchmark

Sugino, Kazuteru; Rimpault, G*; Hayashi, Hideyuki

JNC TN9400 2004-075, 59 Pages, 2005/02

JNC-TN9400-2004-075.pdf:0.68MB

Within the NWP-2 (Innovative core and plant design) of the JNC/CEA bilateral agreement, it was decided to perform GCFR neutronic benchmarks in order to verify the adequacy of computational tools for the definition of GCFR core characteristics. The benchmarks have been performed on two different cores:- A conventional CO2-Cooled fast Reactor (EGCR) core with pin-type fuel- An innovative He-cooled Coated-Particle Fuel (CPF) core Results of the core design characteristics calculated by both JNC and CEA sides agreed quite satisfactorily and it is found that the remaining discrepancies do not influence the core conceptual design specification. Therefore these benchmark results can be used for ensuring some confidence in the GCFR core conceptual designs of both JNC and CEA. For the improvement in the GCFR computational tools, this benchmark has been pointing out some issues. These issues are worth being investigated for improving the design accuracy of GCFR cores.

Journal Articles

None

Hunter; Tikhom, A. V.*; Semen, M. Yu.*; Rimpault, G.*

Proceedings, , 

None

4 (Records 1-4 displayed on this page)
  • 1