Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Nobuo Nakae"'
Publikováno v:
Journal of Nuclear Science and Technology. 54:1190-1200
The objective of this study is to formulate a methodology to predict a fission gas release ratio of MIMAS MOX. An irradiated MIMAS MOX fuel with plutonium rich agglomerates was subjected to elemental analyses by electron probe micro analysis and seco
Publikováno v:
An Advanced Course in Nuclear Engineering ISBN: 9789811028205
This chapter introduces the procedure and basic concept of nuclear design, thermal hydraulic design, and plant dynamics analysis. The outline of reactor physics and thermal hydraulic engineering are also introduced in the first half of this chapter,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d920bd261d17341e4d3b509ecb5ad78e
https://doi.org/10.1007/978-981-10-2821-2_7
https://doi.org/10.1007/978-981-10-2821-2_7
Publikováno v:
Journal of Nuclear Materials. 446:1-9
One of the important issues in the study of Innovative Nuclear Energy Systems is evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems. An approach for evaluating the integrity of the fuel is discussed here based on the proced
Publikováno v:
Journal of Nuclear Materials. 442:309-319
A UO2 fuel with a heterogeneous distribution of 235U was irradiated up to a high burn-up in the Halden Boiling Water Reactor (HBWR). The last 100 days of irradiation were performed with an increased level of linear power. The effect of the heterogene
Autor:
Yuji Kosaka, Takaaki Kitagawa, Nobuo Nakae, Toshikazu Baba, Shigeru Kurematsu, Hiromichi Miura, Hidetoshi Akiyama, Katsuichiro Kamimura, Aya Yoshino
Publikováno v:
Journal of Nuclear Materials. 440:515-523
Thermal property is important because it controls fuel behavior under irradiation. The thermal property change at high burnup of more than 70 GWd/t is examined. Two kinds of MOX fuel rods, which were fabricated by MIMAS and SBR methods, and one refer
Publikováno v:
Progress in Nuclear Energy. 53:1039-1044
One of the important issues in the study of Innovative Nuclear Energy Systems (INES) is the integrity of the fuel system applied. An approach of evaluating fuel system integrity is discussed here based on the procedure currently used in the integrity
Publikováno v:
Journal of Nuclear Science and Technology. 48:524-531
The draft version of the technical standard on fuel for sodium-cooled fast breeder reactor has been prepared by JNES since 2008. It is prepared with the first aim of applying it to the safety licensing of the fuel used in the prototype LMFBR “Monju
Publikováno v:
Journal of the Atomic Energy Society of Japan. 53:118-122
Autor:
Akira Komeno, Motoaki Kashimura, Masato Kato, Hiroki Uno, Kenji Konashi, Hiromasa Sugata, Nobuo Nakae
Publikováno v:
Journal of Nuclear Materials. 393:134-140
In plutonium compounds, the lattice parameter increases due to self-radiation damage by α-decay of plutonium isotopes. The lattice parameter change and its thermal recovery in plutonium and uranium mixed dioxide (MOX) were studied. The lattice param
Publikováno v:
Journal of Nuclear Materials. 389:164-169
Stoichiometries in (U0.7Pu0.3)O2±x and (U0.8Pu0.2)O2±x were analyzed with the experimental data of oxygen potential based on point defect chemistry. The relationship between the deviation x of stoichiometric composition and the oxygen partial press