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Journal Articles

Integrated risk assessment of safety, security, and safeguards

Suzuki, Mitsutoshi

Risk Assessment, p.133 - 151, 2018/02

A integrated risk assessment could be developed to promote synergism between safety, security, and safeguards (3S). One of the synergies of the integrated 3S risk assessment is a 3S by Design approach for new nuclear facilities. In safety, the classical probabilistic risk assessment (PRA) has been developed to estimate the frequency of severe accident using the basic event frequency. Because of recent concern about nuclear security, a vital area identification method based on the ETs/FTs has been explored to protect vital areas of nuclear power plants against sabotage. The different difficulty in applying risk assessment to safeguards is determining the initiation of diversion of nuclear material and misuse, because the diversion of nuclear material and misuse of technology are induced by the motivation of states and intentional acts of facility operation. In this chapter, a balance among 3S risk would be explored to pursue an optimal and a cost-effective management.

JAEA Reports

A Probabilistic assessment code system for derivation of clearance levels of radioactive materials; PASCLR user's manual

Takahashi, Tomoyuki*; Takeda, Seiji; Kimura, Hideo

JAERI-Data/Code 2000-041, 108 Pages, 2001/01

JAERI-Data-Code-2000-041.pdf:4.86MB

no abstracts in English

Journal Articles

Probabilistic accident consequence assessment codes; Second international comparison technical report

W.Nixon*; P.J.Cooper*; C.M.Bone*; S.Acharya*; U.Baeverstam*; J.Ehrhardt*; I.Hasemann*; Steinhauer, C.*; E.G.Diaz*; J.C.Glynn*; et al.

EUR-15109, 0, 338 Pages, 1994/00

no abstracts in English

Journal Articles

LISA Package user guide, Part 2: LISA(Long Term Isolation Safety Assessment) program description and user guide

P.Prado*; A.Saltelli*; Homma, Toshimitsu

EUR-13923, 47 Pages, 1992/00

no abstracts in English

Journal Articles

Radionuclide migration in the geosphere; A 1D advective and dispersive transport module for use in probabilistic system assessment codes

P.Prado*; Homma, Toshimitsu; A.Saltelli*

Radioact. Waste Manage. Nucl. Fuel Cycle, 16(1), p.49 - 68, 1991/00

no abstracts in English

7 (Records 1-7 displayed on this page)
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