Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report

Ball, S.J.

doi:10.2172/1001275

Cited by 31 publications

(39 citation statements)

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“…[Ball et al 2008] The HTTF testing program will provide data for the following three of the six general categories of postulated accident scenarios for the very high temperature gas reactor identified in the NGNP PIRT:…”

Section: Testing Overviewmentioning

confidence: 99%

“…Because of the pressure scaling, there is significant scaling distortion in the natural circulation phase of the PCC for inlet plenum mixing and potentially for the intracore circulation when using prototypical gases [Ball et al 2008]. The purpose of this test is to run a test for which there is less scaling distortion during the natural circulation phase of the PCC for these phenomena.…”

Section: Httf Experiment-014: Complete Loss Of Flow Gas Similaritymentioning

confidence: 99%

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Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

Schult¹,

Bayless²,

Johnson³

et al. 2012

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experiments were only centered on the depressurized conduction cooldown (DCC) scenario, NGNP involvement focused on expanding the experimental envelope of the HTTF to include steady-state operations and also the pressurized conduction cooldown (PCC) scenario.Since DOE has included the HTTF as an ingredient in the NGNP thermal-fluids validation program, several important outcomes should be noted: (a) The reference prismatic reactor design that serves as the basis for scaling the HTTF, became the modular high temperature gas-cooled reactor (MHTGR) (b) To enable the HTTF to operate at more representative steady-state conditions, i.e. with turbulent flow conditions in the core, DOE contributed the resources necessary to allow operation at a steady-state power of 2.2 MW. Consequently the HTTF may operate at steady-state conditions that are more representative of the MHTGR than it could with its initial design components.As this report is being written, the design concept is being finalized but many of the details are still in various stages of review, revision, and approval. In an effort to gain a clear understanding of the correspondence between the projected thermal-fluid behavior of the HTTF in relation to the modular high temperature gas-cooled reactor (MHTGR), a number of analyses have been performed using both systems analysis software (RELAP5-3D) and computational fluid dynamics software. These calculations enable all of the various scaling relationships to be considered concurrently. At a later date, as the HTTF is built, shakedown tests performed, and adjustments to the hardware are completed, a more finalized set of comparisons between the HTTF and the MHTGR will be performed to: (a) examine the correspondence between the two and (b) identify and quantify the HTTF atypicalities.Steady-state simulations of the MHTGR and the HTTF have been performed. The calculations addressed the thermal-hydraulic behavior of both, as well as the thermal stress response of the HTTF.Reference calculations of the MHTGR were performed using the RELAP5-3D computer code. The input model represented the reactor vessel, reactor cavity, and reactor cavity cooling system (RCCS). The core and reflectors were modeled as a series of concentric rings with a coolant gap in between. The reflector rings containing control rod holes were further divided into two rings, one solid and one containing the holes. Unit cells based on a coolant channel were used to model the fuel blocks. Radiation and two-dimensional conduction were modeled to transfer heat from the core through the reflectors to the core barrel, reactor vessel, and RCCS. The RCCS was modeled as an air-cooled system with flow driven by natural convection.The initial HTTF scoping calculations were performed with a scaled-down version of the MHTGR input model. These calculations identified a problem with the facility. With the facility at full power, with prototypical helium inlet and outlet temperatures, the flow through the core was laminar. This resulted in reduced heat transfer f...

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Section: Testing Overviewmentioning

confidence: 99%

Section: Httf Experiment-014: Complete Loss Of Flow Gas Similaritymentioning

confidence: 99%

Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

Schult¹,

Bayless²,

Johnson³

et al. 2012

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show abstract

“…However, during the interim, first-cut PIRTs have been used instead as a guide for the initial R&D work and planning for both prismatic and pebble-bed-type gas-cooled reactors. The first-cut PIRTs are based on observations from seasoned gas-cooled reactor experts and engineering judgment; these factors were used by a team assembled to define the first PIRT for both the prismatic and PBRs and described in Appendix A of Schultz et al [2008] and is documented in detail in Lee, Wei, and Schultz [2005] and Ball et al [2008]. These scenarios and the experiments and modeling used in the investigation of them are listed in Table 1 and described in Section 4.…”

Section: Phenomena Identification and Ranking Tablesmentioning

confidence: 99%

Next Generation Nuclear Plant Methods Technical Program Plan

Schultz¹,

Ougouag²,

Nigg³

et al. 2010

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“…There are six NRC NGNP PIRTs at this writing. Five are documented as Volumes 2 through 6 of NUREG/CR-6944 (Ball and Fisher 2008), which is an umbrella document with Volume 1 providing an introduction to the PIRT process and summaries of the five individual PIRTs. The topics addressed by these PIRTs are thermal/accidents, fission product transport, high temperature materials, graphite, and hydrogen and process heat.…”

Section: Nrc Pirtsmentioning

confidence: 99%

HTGR Mechanistic Source Terms White Paper

Moe¹

2010

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Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report

Cited by 31 publications

References 0 publications

Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

Next Generation Nuclear Plant Methods Technical Program Plan

HTGR Mechanistic Source Terms White Paper

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