Gas-chromatographic examination of the accumulation of3H,85Kr, and133Xe in the protective gas, sodium coolant, and constructional materials of the BR-10

Moseev, L. I.; Aristarkov, N. N.; Efimov, I. A.; Piskunov, V.N.; Smolyakov, V. I.; Shkuro, S. I.

doi:10.1007/bf01118201

Cited by 1 publication

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References 3 publications

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“…Systems for detecting leaks in fuel-element cladding during reactor operation [6][7][8], systems for locating fuel assemblies with defective (with respect to gas or fuel) fuel-element cladding in external systems after removal from the reactors, and a spectrometric circuit on a radioactive loop [5] were developed and adopted. Fuel elements with different fuel (plutonium dioxide, uranium carbide, uranium metal, uranium nitride), with an artificial defect in different locations and of different forms in fuel-element cladding, the development of a defect during irradiation, and the response of the system that monitors cladding seals were investigated.…”

Section: Br-10 Research and Experimental-design Work Used To Develop mentioning

confidence: 99%

History of the engineering and scientific-technical contribution of BR-5 and BR-10 reactors to the development of fast sodium-cooled reactors

2009

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The first experimental sodium-cooled reactor BR-5 in Europe was built and put into operation in a record short time -three years (1956)(1957)(1958)(1959). The main goal of building such a reactor was to master the use of sodium coolant and sodium equipment under radiation-hazardous operating conditions. It is shown that the reactor made it possible to solve other problems also. The first sodium apparatus, systems for monitoring and purifying the coolant, and methods and facilities which were later used in the development of fast power reactors were mastered on BR-5. The components of successful multiyear (43 years) operation and the results of investigations are presented. The article focuses primarily on the experiential aspects which were later used to develop and operate subsequent fast reactors.

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Section: Br-10 Research and Experimental-design Work Used To Develop mentioning

confidence: 99%

History of the engineering and scientific-technical contribution of BR-5 and BR-10 reactors to the development of fast sodium-cooled reactors

2009

View full text Add to dashboard Cite

show abstract

Gas-chromatographic examination of the accumulation of3H,85Kr, and133Xe in the protective gas, sodium coolant, and constructional materials of the BR-10

Cited by 1 publication

References 3 publications

History of the engineering and scientific-technical contribution of BR-5 and BR-10 reactors to the development of fast sodium-cooled reactors

History of the engineering and scientific-technical contribution of BR-5 and BR-10 reactors to the development of fast sodium-cooled reactors

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