2017
DOI: 10.1051/epjn/2017025
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Independent assessment for new nuclear reactor safety

Abstract: Abstract. A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On the one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results… Show more

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Cited by 9 publications
(7 citation statements)
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“…The stakes as so ci ated with the cost of the NPP, the com plex ity of the sys tem and the po ten tial im pact of ra di a tion upon the hu mans and the en vi ronment jus tify IA: safety must be dem on strated by experts in de pend ent from de sign ers and own ers of the con cerned sys tem who take a ben e fit from the op er ation of the same sys tem. The im ple men ta tion of the IA re quire ment may re veal un fea si ble out side BEPU, [11]; namely this is the only log i cal ap proach for the licen sor for get ting the IA of the li censee sub mis sion: the un cer tainty in in put pa ram e ters is de rived in depend ently and sub sti tutes, and even tu ally is con sis tent with, the con ser va tism of the li censee pos si bly based on pro pri etary (best es ti mate) in for ma tion.…”
Section: The Bepu-qa and Alara-bepu-iamentioning
confidence: 99%
“…The stakes as so ci ated with the cost of the NPP, the com plex ity of the sys tem and the po ten tial im pact of ra di a tion upon the hu mans and the en vi ronment jus tify IA: safety must be dem on strated by experts in de pend ent from de sign ers and own ers of the con cerned sys tem who take a ben e fit from the op er ation of the same sys tem. The im ple men ta tion of the IA re quire ment may re veal un fea si ble out side BEPU, [11]; namely this is the only log i cal ap proach for the licen sor for get ting the IA of the li censee sub mis sion: the un cer tainty in in put pa ram e ters is de rived in depend ently and sub sti tutes, and even tu ally is con sis tent with, the con ser va tism of the li censee pos si bly based on pro pri etary (best es ti mate) in for ma tion.…”
Section: The Bepu-qa and Alara-bepu-iamentioning
confidence: 99%
“…Safety Margin (SM) is a well-known concept in NRS: suitable safety margins must be demonstrated and are part of design, construction and operation of existing reactors, D'Auria et al 2017c, andD'Auria et al 2017d.…”
Section: The Extended Safety Margin Detection (E-smd)mentioning
confidence: 99%
“…The additional barrier B5 is constituted by a combination of the following elements, which have a heterogeneous nature and role: the As Low As Reasonably Achievable (ALARA) principle, the Independent Assessment (IA) requirement, the Best Estimate Plus Uncertainty (BEPU) approach, the Extended Safety Margin (E-SM) concept and the Emergency Rescue Team (ERT), now a virtual reality. ALARA, IA, BEPU and E-SM are discussed in [11] with more details given in [2], [12] and [13] and ERT is introduced in [14]. The elements are shortly discussed in sections 3.1 and 3.2, distinguishing between 'software' and 'hardware' and their combined role is outlined in section 3.3.…”
Section: The Elements Of the Additional Barriermentioning
confidence: 99%
“…The IA requirement, although established since the early developments of nuclear technology, later on became of difficult application owing to the increasing sophistication of NPP which implies (more) proprietary data needed for safety demonstration [13].…”
Section: The 'Software' Elementsmentioning
confidence: 99%
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