Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 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

Overview of plasma-material interaction experiments on EAST employing MAPES

Ding, F.*; Luo, G.-N.*; Pitts, R.*; Litnovsky, A.*; Gong, X.*; Ding, R.*; Mao, H.*; Zhou, H.*; Wampler, W. R.*; Stangeby, P. C.*; et al.

Journal of Nuclear Materials, 455(1-3), p.710 - 716, 2014/12

 Times Cited Count:24 Percentile:88.28(Materials Science, Multidisciplinary)

Journal Articles

FUJI, an initial sintering comparison test for pelletized-, sphere-pac- and vipac-fast breeder reactor mixed oxide fuel

Bart, G.*; Bakker, K.*; Hellwig, C.*; Kihara, Yoshiyuki; Ozawa, Takayuki; Wallin, H.*; Shigetome, Yoshiaki

Journal of Nuclear Science and Technology, 44(3), p.329 - 336, 2007/03

 Times Cited Count:4 Percentile:37.26(Nuclear Science & Technology)

Within the FUJI collaboration program among Japan Atomic Energy Agency (JAEA, former JNC), Paul Scherrer Institute (PSI, Switzerland) and Nuclear Research and Consultancy Group (NRG, the Netherlands) the production paths of plutonium and neptunium mixed oxide- (sphere-pac- and vipac-) particle fuels (20wt% Pu and 5wt% Np) are tested as well as the initial sintering and power-to-melt behavior under simulated FBR conditions. The various fuel forms were produced at PSI under the support of JNC, the irradiations were accomplished at High Flux Reactor (HFR) in Petten, the post irradiation examinations are being achieved mainly at NRG and the fuel modelling being performed at JNC and PSI. The present paper reviews mainly the project planning, fuel behaviour- pre-calculations and the fuel- and fuel segment- production. A short overview of the irradiation conditions and ceramographic post irradiation examination analyses is also given.

Journal Articles

PIE results of comparative irradiation tests in HFR for sphere-pac fuel, pellet fuel and vipac fuel

Morihira, Masayuki; Hellwig, C.*; Bakker, J.*; Nakamura, Masahiro; Ozawa, Takayuki; Bart, G.*; Kihara, Yoshiyuki

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

Comparative irradiation tests of sphere-pac fuel (SPF) with pellet type fuel (PF) and vipac fuel (VPF) were performed in the HFR in the Netherlands in a framework of the collaboration project amog JNC, PSI and NRG. Three restructuring tests and a powet-to-melt test were performed in 2004 and 2005 to obtain rerestructuring data of SPF in the beginning of life as well PTM data. This paper focuses the result of irradiation tests and post irradiation examinations.

JAEA Reports

Final Report of the FUJI Project Concerning the Research and Development of Advanced Sphere-Pac Fuel among JNC, PSI and NRG

Morihira, Masayuki; Nakamura, Masahiro; Ozawa, Takayuki; Kihara, Yoshiyuki; Hellwig, C.*; Ingold, F.*; Bakker, K.*

JNC TY8400 2005-006, 320 Pages, 2005/08

JNC-TY8400-2005-006.pdf:18.0MB

The collaboration project concerning sphere-pac fuel (SPF) among JNC, PSI and NRG was performed from 1996 till 2005. Total sixteen fuel segments (eight pins) of three types of fuel were fabricated in PSI. Two SPF segments contained 5%Np in addition to 20%Pu-MOX. Other segments contained no Np. The fuel microsphere for SPF was fabricated by the internal gelation process. The trial to apply the internal gelation process to Np-MOX fabrication was successfully attained. The test pins were transported to Petten in the Netherlands in September 2003 and assembling of the sample holders was done. Three steady state irradiation tests and one power-to-melt test were performed in HFR. Two test pins (four segments) were irradiated every tests simultaneously. The former tests were performed mainly to obtain the restructuring data of SPF in the early beginning of irradiation. The later was done to evaluate PTM linear heat rate of SPF with the reference data for pellet fuel. The irradiation tests were performed in January to March 2004 and December 2004 to March 2005. Post irradiation examination was completed in August 2005. In this project the irradiation tests in HFR was doubtless main task but so many other works were also performed i.e. transfer of the technology concerning modeling and design of sphere-pac fuel from PSI to JNC, additional destructive PIE of IFA-550.11 fuel (a power ramp test of sphere-pac fuel segment irradiated in the Gösgen PWR), fabrication tests in PSI, etc. This report summarized the planning of the irradiation tests, fuel design, result of fabrication, irradiation, post irradiation examination and data analysis. SPF design codes, DIRAD-S, SIMPLE-S which was developed by implanting SPF models of PSI into the pellet design codes in JNC, were verified with the irradiation test data in this project to show good accuracy.

Journal Articles

Vipac Fuel Fabrication for Irradiation Test of the FUJI Project

Shigetome, Yoshiaki; Kono, Shusaku; Hellwig, C.*; Heimgartner, P.*

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1342 - 1347, 2003/00

None

Oral presentation

Comparison of the fuel performance for advanced FBR cycle systems, FUJI project, 11; Modeling results of a sphere-pac fuel design code, DIRAD-S

Nakamura, Masahiro; Morihira, Masayuki; Kihara, Yoshiyuki; Sekine, Nobuyuki*; Hellwig, C.*; Bakker, K.*

no journal, , 

In the framework of collaboration among JNC (now JAEA), PSI and NRG called "he FUJI project" calculation results of a sphere-pac fuel design code, DIRAD-S were compared to the PIE results. DIRAD-S contains a thermal conductivity model of a particle bed, named SPACON, and mechanistic models for the necking calculation between particles. The calculation results had good agreement with the PIE results.

6 (Records 1-6 displayed on this page)
  • 1