Published April 2017 | Version v1
Miscellaneous Metadata-only

Development of dynamic probabilistic risk assessment model for PWR using simplified plant simulation method

Creators

  • 1. Nagoya Univ., Nagoya, Aichi (Japan)

Description

The CMMC (Continuous Markov Monte Carlo) coupling method is proposed for quantifying accident scenarios that have time-dependence in accident progression and inter-dependence of individual events. In order to analyze large number of samples within realistic computing time, we developed a simplified accident progression analysis model and coupled the simplified model to the CMMC method. Large number of samples for station black out in PWR were analyzed using the random sampling method based on the CMMC method considering uncertainty of decay heat from a core. As a result, uncertainties of event initiation time and FPs release ratio to the atmosphere are estimated. (author)

Part of:
Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)

Additional details

Publishing Information

Imprint Title
Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
Imprint Pagination
2573 p.
Journal Page Range
6 p.

Conference

Title
2017 international congress on advances in nuclear power plants
Acronym
ICAPP2017
Dates
24-25 Apr 2017; 26-28 Apr 2017
Place
Fukui (Japan); Kyoto (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
49033481
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT REMOVAL; CONTAINMENT BUILDINGS; FISSION PRODUCT RELEASE; MONTE CARLO METHOD; NATURAL CONVECTION; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR COOLING SYSTEMS; REACTOR VESSELS; RISK ASSESSMENT; STATION BLACKOUT; STEAM GENERATORS; TRANSIENTS
Descriptors DEC
ACCIDENTS; BOILERS; BUILDINGS; CALCULATION METHODS; CONTAINERS; CONTAINMENT; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17401.pdf; 11 refs., 7 figs., 2 tabs.