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Source term assessment of spent fuel in wet storage

TLDR
In this paper, the authors presented the obtained results in estimation of activity of spent fuel activity, EK-10 and C-36, which is in wet storage at Magurele in Romania.
Abstract
Estimarea activitaţii combustibilului nuclear uzat depozitat in bazinele cu apa, este importanta pentu analiza degradarii tecii de combustibil datorita coroziunii. Aceasta estimare permite personalului de operare sa coreleze valoarea activitaţii apei din bazine cu numarul de elemente care prezinta defecte de teaca. Prezentul articol prezinta rezultatele obţinute in estimarea activitaţii combustibilului nuclear uzat EK-10 si C-36 ce este depozitat la Magurele. Pentru estimarea starii termenului sursa s-au utilizat de coduri de calcul ce valorifica istoria exploatarii combustibilului. Calculele sunt importante pentru estimarea nivelului radionuclizilor (produsi de fisiune, gaze de fisiune, produsi de activare) din interiorul combustibilui uzat atsfel incât sa poata fi luate masurile necesare pentru protecţia impotriva radiaţiei si prevenirea eliberarii de material radioactiv din combustibil in mediu. An estimate of spent fuel activity in storage ponds is important to any analysis of actual cladding failure due to corrosion. This allows the operator the possibility to correlate the estimated values of the activity to the actual values in water samples, thereby predicting the number of failing fuel elements. This paper presents the obtained results in estimation of activity of spent fuel activity, EK-10 and C-36, which is in wet storage at Magurele in Romania. Validated computer codes and history of fuel exploitation have been used to estimate the actual state fuel source term. Also the computation is important for estimation of radionuclides level (fission products, fission gasses, activation products) presents in spent fuel inside so for establishing of the necessary measures which could be taken for radiation protection and for prevention of radionuclides release into the environment.

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Estimation of radionuclide transfer times in the geological layers of saligny site

TL;DR: In this paper, the authors describe the assessment of 60 Co and 137 Cs transfer times in the geological layers of Saligny site which is selected for the construction of a radioactive waste repository.