Author: Chang Kue Park
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160
Book Description
Reliability Analysis of the Emergency Core Cooling System of the Massachusetts Institute of Technology Reactor II
Author: Chang Kue Park
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160
Book Description
Emergency Core Cooling
Author: United States. Advisory Task Force on Power Reactor Emergency Cooling
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 242
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 242
Book Description
Reliability Analysis of a Passive Cooling System Using a Response Surface with an Application to the Flexible Conversion Ratio Reactor
Author: Christopher Joseph Fong
Publisher:
ISBN:
Category :
Languages : en
Pages : 128
Book Description
A comprehensive risk-informed methodology for passive safety system design and performance assessment is presented and demonstrated on the Flexible Conversion Ratio Reactor (FCRR). First, the methodology provides a framework for risk-informed design decisions and as an example two design options for a decay heat removal system are assessed and quantitatively compared. Next, the reliability of the system is assessed by quantifying the uncertainties related to system performance and propagating these uncertainties through a response surface using Monte Carlo simulation. Finally, a sensitivity study is performed to measure the relative effects of each parameter and to identify ways to maintain, improve, and monitor system performance.
Publisher:
ISBN:
Category :
Languages : en
Pages : 128
Book Description
A comprehensive risk-informed methodology for passive safety system design and performance assessment is presented and demonstrated on the Flexible Conversion Ratio Reactor (FCRR). First, the methodology provides a framework for risk-informed design decisions and as an example two design options for a decay heat removal system are assessed and quantitatively compared. Next, the reliability of the system is assessed by quantifying the uncertainties related to system performance and propagating these uncertainties through a response surface using Monte Carlo simulation. Finally, a sensitivity study is performed to measure the relative effects of each parameter and to identify ways to maintain, improve, and monitor system performance.
Risk-informed Design Guidance for a Generation-IV Gas-cooled Fast Reactor Emergency Core Cooling System
Author: Michael James Delaney
Publisher:
ISBN:
Category :
Languages : en
Pages : 117
Book Description
Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling system design through PRA insights was utilized based upon the preliminary stage of the reactor design and activities currently ongoing in the nuclear industry, regulator, and universities regarding advanced reactors. Advanced reactor designs also face an uncertain regulatory environment. It was concluded from the move towards risk- informed regulations of current reactors, that there will be some level of probabilistic insights in the regulations and supporting regulatory documents for advanced, "Generation-IV" nuclear reactors. The four-step methodology is moreover used to help designers analyze designs under potential risk-informed regulations and predict design justifications the regulator will require during the licensing process. The iterative design guidance methodology led to a reduction of the CDF contribution due to a LOCA of over three orders of magnitude from the baseline ECCS design (from 1.19x10-5 to 6.48x10-8 for the 3x100% loop configuration) and potential ECCS licensing issues were identified. This illustrates the value of formal design guidance based upon PRA.
Publisher:
ISBN:
Category :
Languages : en
Pages : 117
Book Description
Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling system design through PRA insights was utilized based upon the preliminary stage of the reactor design and activities currently ongoing in the nuclear industry, regulator, and universities regarding advanced reactors. Advanced reactor designs also face an uncertain regulatory environment. It was concluded from the move towards risk- informed regulations of current reactors, that there will be some level of probabilistic insights in the regulations and supporting regulatory documents for advanced, "Generation-IV" nuclear reactors. The four-step methodology is moreover used to help designers analyze designs under potential risk-informed regulations and predict design justifications the regulator will require during the licensing process. The iterative design guidance methodology led to a reduction of the CDF contribution due to a LOCA of over three orders of magnitude from the baseline ECCS design (from 1.19x10-5 to 6.48x10-8 for the 3x100% loop configuration) and potential ECCS licensing issues were identified. This illustrates the value of formal design guidance based upon PRA.
Unavailability Analysis of the Reactor Core Isolation Cooling System of Pilgrim Nuclear Power Station
Emergency Core Cooling Systems for Light-water-cooled Nuclear Reactors: Proposed Rulemaking
A Selected Bibliography on Emergency Core Cooling Systems (ECCS) for Light-water Cooled Power Reactors (LWRs)
Author: William B. Cottrell
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 194
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 194
Book Description
An Experimental Study of the Fluid Flow Behavior of the Emergency Core Coolant to the Top of the Core of a Nuclear Reactor
Author: Navin Jaffer
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 118
Book Description
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 118
Book Description
Energy Research Abstracts
Analysis of Degraded Core Cooling in Light Water Reactors
Author: Samir Mahmood Mohammed
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 284
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 284
Book Description