نتایج جستجو برای: fission reactor coolant

تعداد نتایج: 45549  

2013
A. Blanc G. de France F. Drouet M. Jentschel U. Köster C. Mancuso P. Mutti J. M. Régis G. Simpson T. Soldner C. A. Ur W. Urban

One way to explore exotic nuclei is to study their structure by performing -ray spectroscopy. At the ILL, we exploit a high neutron flux reactor to induce the cold fission of actinide targets. In this process, fission products that cannot be accessed using standard spontaneous fission sources are produced with a yield allowing their detailed study using high resolution -ray spectroscopy. This i...

2006
C.P.C. Wong S. Malang M. Sawan M. Dagher S. Smolentsev B. Merrill M. Youssef S. Reyes D. K. Sze N. B. Morley S. Sharafat P. Calderoni R. Kurtz P. Fogarty M. Abdou

An attractive blanket concept for the fusion reactor is the dual coolant Pb–17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb–17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetoh...

1999
S. Martorell

When a nuclear power plant is in shutdown conditions for refuelling, the reactor coolant system water level is reduced. This situation is known as mid-loop operation, and the residual heat removal (RHR) system is used to remove the decay power heat generated in the reactor core. In mid-loop conditions, some accidental situations may occur with not a negligible contribution to the plant risk, an...

2008
Y. Kawamura K. Isobe Y. Iwai H. Nakamura K. Kobayashi T. Hayashi T. Yamanishi

A water cooling solid breeder blanket is a prime candidate of the blanket of the fusion reactor in Japan. In this case, the blanket tritium recovery system will be composed of three processes: tritium recovery from the helium sweep gas as hydrogen, that as water vapor and tritium recovery from the coolant water. For these processes, the present authors have proposed a set of advanced systems, a...

Journal: :Nuclear Technology 2021

The Molten Salt Reactor Experiment (MSRE), which operated at Oak Ridge National Laboratory from 1965 to 1969, was an experimental reactor that used UF4 fuel dissolved in molten fluoride salt. Criticality achieved when the salt mixture passed through graphite-moderated core region. Therefore, because and fission products flowed system, delayed neutron precursors were not confined core, decay hea...

2002
R S Raghavan

A natural nuclear fission reactor with a power output of 3-to 10 Terawatt at the center of the earth has been proposed as the energy source of the earth’s magnetic field. The proposal can be directly tested by a massive liquid scintillation detector that can detect the signature spectrum of antineutrinos from the geo-reactor as well as the direction of the antineutrino source. Such detectors ar...

2006
Daniel Cubicciotti

Vaporization of fission products and certain other materials is estimated for the extreme environmental conditions projected for severe reactor accidents. Partial pressures of gaseous species are calculated from thermochemical data or estimates. Mounts of vapor transported material are evaluated from projected gas flows during two phases of a hypothetical accident--( a) core dry out phase and (...

1996
T. Mukaiyama

One of the techniques of minor actinides transmutation is to recycle these nuclides into fission reactors. Two concepts of a minor actinides burner reactor with very hard neutron energy spectrum as well as very high neutronjlux me discussed. The fuel cycle facilities for these burner reactors am assessed to discuss the technical feasibili~ of these reactors. Transmutation of minor actinide in b...

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