Analyses of Unscrammed Events Postulated for the Prism Design

Tuyle, G.J. Van; Slovik, G.C.; Kennett, R.J.; Chan, B.C.; Aronson, A.

doi:10.13182/nt90-a34426

Cited by 12 publications

(3 citation statements)

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“…The model is applied to the two types of reactors. There are modular of fast reactor design like PRISM reactor [9] and modular high temperature gas-cooled reactor design like HTR-M reactor [8]. PRISM reactor is fuelled by 239 Pu, the HTR-M reactor is fuelled by 235 U as fissile nuclides.…”

Section: Discussionmentioning

confidence: 99%

“…In this study, a new computer program has been developed for simulating the reactor dynamic behavior during reactivity induced transients, and it has been used for the analysis of specified reactivity -initiated accidents considered in several cases. We introduce the two models reactors with system parameters, which are characteristic for modular high temperature gas-cooled reactor design like HTR-M [8] and modular fast reactor design like PRISM [9]. For simplicity, we refer to these models of two reactors as HTR-M and PRISM (Tables 5 and 6).…”

Section: Reactivity Initiated Accidentmentioning

confidence: 99%

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Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

Saad¹,

Mohammed²,

Mansour³

2013

JMSE-B

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Understanding of the time-dependent behavior of the neutron population in nuclear reactor in response to either a planned or unplanned change in the reactor conditions, is a great importance to the safe and reliable operation of the reactor. In the present work, the point kinetics equations are solved numerically using stiffness confinement method (SCM). The solution is applied to the kinetics equations in the presence of different types of reactivities and is compared with different analytical solutions. This method is also used to analyze reactivity induced accidents in two reactors. The first reactor is fueled by uranium and the second is fueled by plutonium. This analysis presents the effect of negative temperature feedback with the addition positive reactivity of control rods to overcome the occurrence of control rod ejection accident and damaging of the reactor. Both power and temperature pulse following the reactivity-initiated accidents are calculated. The results are compared with previous works and satisfactory agreement is found.

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Section: Discussionmentioning

confidence: 99%

Section: Reactivity Initiated Accidentmentioning

confidence: 99%

Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

Saad¹,

Mohammed²,

Mansour³

2013

JMSE-B

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“…In ATWS analyses of Power Reactor Inherent Safety Module (PRISM), the heat transfer delay constant of CRD and RV-wall temperatures were assumed to be 28 and 700 s, respectively. 35) In the present analysis, the delay constant from the RV upper plenum to the CRD is assumed to be 50 s by a primitive evaluation. 36) In the present analysis, the thermal expansion of RV is ignored since the delay constant of RV expansion is long enough and the RV region which causes thermal expansion is limited by the IHX and EMPs arrangement.…”

Section: Evaluation Of the Plant 1 Passive Safetymentioning

confidence: 99%

A Feasibility Study on a Small Sodium Cooled Reactor as a Diversified Power Source

Chikazawa¹,

Okano²,

Hori³

et al. 2006

J. Nucl. Sci. Technol.

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A conceptual design study of a small sized sodium cooled reactor with 165 MWe output with a metallic fuel, which aimed at the application for the diversified power supply has been carried out. A metal fuel core has been developed with 550C core outlet temperature and 20 years core life time by utilizing the three zone core having different Zr contents in U-Pu-Zr of metal fuel. Major components in the nuclear steam supply system has been design and safety analyses has been performed to evaluate economical and safety potential of the concept. ATWS analyses show the passive safety feature of this concept adopting control rod driver-line (CRD) expansion reactivity and prolongation of electromagnetic pump (EMP) coastdown. Enhancing passive safety features, a improved upper inner structure enhancing CRD expansion and a reliable power source for EMP has been proposed. Though construction cost in first of a kind (FOAK) does not satisfy the economical goal, the present concept has potential for achieving the economical goal in Nth of a kind (NOAK) considering learning effect.

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Dynamics of passive reactor shutdown

Dam

1996

Progress in Nuclear Energy

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Analyses of Unscrammed Events Postulated for the Prism Design

Cited by 12 publications

References 0 publications

Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling

A Feasibility Study on a Small Sodium Cooled Reactor as a Diversified Power Source

Dynamics of passive reactor shutdown

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