Testing the hermeticity (air tightness) of fuel elements in the BR-5 reactor

Efimov, I. A.; Mamaev, L.I.; Filonov, Vladislav

doi:10.1007/bf01371957

Cited by 3 publications

(2 citation statements)

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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

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“…Too little information on BR-10 fuel-failure has been received to Include In this review. It is Interesting to note that BR-5 had an estimated 38 g of 235 U in the primary circuit coolant in 1969 [7]. The Fermi Subassembly Meltdown.…”

Section: In-reactor Operating-experience and Experimentsmentioning

confidence: 99%

LMFBR Operational and Experimental In-Core, Local-Fault Experience, Primarily With Oxide Fuel Elements

Warinner

1983

Journal of Engineering for Power

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Case-by-case reviews of selective world experience with severe local faults, particularly fuel failure and fuel degradation, are reviewed for two sodium-cooled thermal reactors, several LMFBRs, and LMFBR-fuels experiments. The review summarizes fuel-failure frequency and illustrates the results of the most damaging LMFBR local-fault experiences of the last twenty years, beginning with BR-5, and including DFR, BOR-60, BR2’s MFBS-and Mol-loops experiments, Fermi, KNK, Rapsodie, EBR-II, and Treat-D2. Local-fault accommodation is demonstrated and a need to more thoroughly investigate delayed-neutron and gaseous-fission-product signals is highlighted in view of uranate formation, observed blockages, and slow fuel-element failure-propagation.

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Some yield characteristics of short-lived fission products in a sodium heat-transfer agent

Efimov¹,

Lopatin²,

Mamaev³

et al. 1977

At Energy

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Testing the hermeticity (air tightness) of fuel elements in the BR-5 reactor

Cited by 3 publications

References 0 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

LMFBR Operational and Experimental In-Core, Local-Fault Experience, Primarily With Oxide Fuel Elements

Some yield characteristics of short-lived fission products in a sodium heat-transfer agent

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