Tritium solid targets for intense D-T neutron production and the related problems

Sumita, Kenji

doi:10.1016/0168-9002(89)90165-4

Cited by 13 publications

(7 citation statements)

References 5 publications

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“…In an adiabatic environ ment, this heat density would raise the titanium tritride temperature at a rate of 10 8 K s −1 . Fortunately, conduction releases heat limiting the temperature excursion to ~200 K; this demands the rotation of the target >5000 rpm [67,121]. Despite these severe conditions, the neutron yield obtained remains three orders of magnitude lower than the expected in a fusion reactor.…”

Section: 131d-t Neutron Sourcesmentioning

confidence: 99%

An assessment of the available alternatives for fusion relevant neutron sources

Knaster¹

2018

Nucl. Fusion

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The discovery of void swelling in neutron-irradiated stainless steels by Cawthorne and Fulton in 1966 showed that radiation effects would seriously affect the lifetime of fission reactors. A few years later, in the early 1970s, serious damage levels were observed in core components of the first commercial fission reactors that had been in operation for one decade. Driven by the harder neutron spectrum, the fusion community was impelled to explore the technical possibilities to make available a fusion relevant neutron source to anticipate the difficulties faced by the fission reactors community and ensure the long-term operation of a fusion reactor. In 1976, the conclusions of the first review published announced the assets and drawbacks of the different possibilities, which today despite the four decades passed and the sound technological advancements, continue being basically the same. A suitable neutron spectrum can be theoretically obtained both from plasma-based or accelerators based facilities with either gas, liquid or solids targets. Needed facilities performances, available irradiation volumes that the concept allow and cost are at stake. In the past, the cost of the most promising facility based on stripping the neutron from a deuteron on a lithium target was misleadingly peered with that of a fusion reactor. A tokamak with sufficient volume to irradiate equipment under fusion relevant conditions will be likely available in the future once commercial fusion reactors have become a reality; unfortunately, this concept does not match the needs timely, and is unrealistic w.r.t. its costs nowadays with worldwide efforts prioritizing ITER. In this article, we will focus on the technical aspects and assess the present maturity of different existing possibilities based on nowadays technologies to count with neutrons at a suitable flux and spectrum to characterize and qualify fusion materials to be timely ready with our world fusion roadmaps.

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Section: 131d-t Neutron Sourcesmentioning

confidence: 99%

An assessment of the available alternatives for fusion relevant neutron sources

Knaster¹

2018

Nucl. Fusion

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“…It is possible to achieve average irradiation capability of some 3 dpa/fpy over 50 cm 3 and about 2.4 dpa/fpy over 500 cm 3 . Maximum peak flux is 3.7 × 10 13 n/cm 2 /s.…”

Section: Introductionmentioning

confidence: 98%

“…Two ions beams (one deuterium and one tritium) deliver to a rotating target a power of 8 MW on both of two facing surfaces (16 MW on the two targets). A high irradiation zone of about 150 cm 3 and neutron flux of about 2.3 × 10 13 n/cm 2 /s producing about 2 dpa/fpy is available. In addition, volume up to 500 cm 3 is used for intense irradiation exceeding 1.5 dpa/fpy.…”

Section: Introductionmentioning

confidence: 99%

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Design optimization and performances of New Sorgentina Fusion Source (NSFS) supporting materials research

Camprini¹,

Bernardi²,

Pillon

et al. 2015

Fusion Engineering and Design

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“…Currently, several D–T neutron generators have been built, such as RTNS‐II in USA , SNEG‐13 in Russia , FNS in Japan , and FNG in Italy , which generally have the neutron yield of 10 11 –10 13 n/s. China has also developed the neutron generators like CPNG‐6 , ZF‐300 , and PD‐300, which generally have the neutron yield of 10 10 –10 12 n/s.…”

Section: Introductionmentioning

confidence: 99%

Development of high intensity D-T fusion neutron generator HINEG

2016

Int J Energy Res

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Abstract：A high intensity D-T fusion neutron generator (HINEG) is keenly needed for the research and development (R&D) of nuclear technology and safety of the advanced nuclear energy system, especially for the radiation protection and shielding. The R&D of HINEG includes two phases: HINEG-I and HINEG-II. HINEG-I is designed to have both the steady beam and pulsed beam. The neutron yield of the steady beam is up to 10 12 n/s. The width of pulse neutron beam is less than 1.5 ns. HINEG-I is used for the basic neutronics study, such as measurement of nuclear data, validation of neutronics methods and software, validation of radiation protection and so on. HINEG-II aims to generate a high neutron yield of 10 13 n/s neutrons by adopting high speed rotating tritium target system integrated with jet/spray array enhanced cooling techniques, and can further upgrade to obtain neutron yield of 10 14~1 0 15 n/s by using of accelerators-array in a later stage. HINEG-II can be used for fundamentals research of nuclear technology including mechanism of materials radiation damage and neutronics performance of components, radiation shielding as well as other nuclear technology applications.

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Tritium solid targets for intense D-T neutron production and the related problems

Cited by 13 publications

References 5 publications

An assessment of the available alternatives for fusion relevant neutron sources

An assessment of the available alternatives for fusion relevant neutron sources

Design optimization and performances of New Sorgentina Fusion Source (NSFS) supporting materials research

Development of high intensity D-T fusion neutron generator HINEG

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