Operating history report for the Peach Bottom HTGR. Volume I. Reactor operating history

Scheffel, W.J.; Baldwin, N.L.; Tomlin, R.W.

doi:10.2172/7136159

Cited by 5 publications

(6 citation statements)

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“…The impurity levels are low but can interfere with experiments. In reviewing past operating experiences in the nuclear industry, the Peach Bottom 1 high temperature helium-gas cooled fission reactor had the following impurity levels in its coolant helium during a plant startup following a maintenance outage (Scheffel, 1976 2.4 CO 9.9…”

Section: Fmea Conclusion and Recommendationsmentioning

confidence: 99%

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Cadwallader

2013

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This report presents the results of a preliminary failure modes and effects analysis (FMEA) of a candidate design for the ITER Disruption Mitigation System. This candidate is the Massive Gas Injection System that provides machine protection in a plasma disruption event. The FMEA was quantified with "generic" component failure rate data as well as some data calculated from operating facilities, and the failure events were ranked for their criticality to system operation. v CONTENTS ABSTRACT

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Section: Fmea Conclusion and Recommendationsmentioning

confidence: 99%

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Cadwallader

2013

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“…In the United States, Peach Bottom Atomic Power Station 1 [6], UHTREX [7] and Fort Saint Vrain [8] PBMR design will be capable of providing an outlet temperature of up to 950 • C, though it is unknown at this time when the PBMR design will be pushed to operate at this limit. In the United States, the U.S. Department of Energy is planning start-up of the Next Generation Nuclear Plant (NGNP) [13] by 2021, which will be capable of providing high-temperature heat at temperatures up to 950 • C for generating electricity or for providing heat to chemical process applications.…”

Section: Suitability Of High-temperature Gas-cooled Nuclear Reactorsmentioning

confidence: 99%

Nuclear powered CO₂ capture from the atmosphere

Sherman

2009

Env Prog and Sustain Energy

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A process for capturing CO 2 from the atmosphere was recently proposed. This process uses a closed cycle of sodium and calcium hydroxide, carbonate, and oxide transformations to capture dilute CO 2 from the atmosphere and to generate a concentrated stream of CO 2 that is amenable to sequestration or subsequent chemical transformations. In one of the process steps, a fossilfueled lime kiln is needed, which reduces the net CO 2 capture of the process. It is proposed to replace the fossil-fueled lime kiln with a modified kiln heated by a high-temperature nuclear reactor. This will have the effect of eliminating the use of fossil fuels for the process and increasing the net CO 2 capture. Although the process is suitable to support sequestration, the use of a nuclear power source for the process provides additional capabilities, and the captured CO 2 may be combined with nuclear-produced hydrogen to produce liquid fuels via Fischer-Tropsch synthesis or other technologies. Conceivably, such plants would be carbon-neutral, and could be placed virtually anywhere without being tied to fossil fuel sources or geological sequestration sites.

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“…20 However, the equilibrium constant 2 K of the reaction in Equation (31), which is the isotope exchange reaction between HT and H 2 SO 4 , was not provided in the Atomic Society of Japan (1982 In the numerical analysis model for the SI process developed for this study, the following strategies and assumptions were proposed: (Scheffel, Baldwin, and Tomlin 1976;Wichner and Dyer 1979) was the first installation of an HTGR in the United States. The plant operated from 1967 to 1974.…”

Section: Purification System Modelmentioning

confidence: 99%

Tritium Movement and Accumulation in the NGNP System Interface and Hydrogen Plant

Ohashi¹,

Sherman²

2007

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Tritium movement and accumulation in a Next Generation Nuclear Plant with a hydrogen plant using a high-temperature electrolysis (HTE) process and a thermochemical water-splitting Sulfur-Iodine (SI) process are estimated by the numerical code THYTAN as a function of design, operational, and material parameters. Estimated tritium concentrations in the hydrogen product and in process chemicals in the hydrogen plant of the Next Generation Nuclear Plant using the HTE process are slightly higher than the drinking water limit defined by the U.S. Environmental Protection Agency and the limit in the effluent at the boundary of an unrestricted area of a nuclear plant as defined by the U.S. Nuclear Regulatory Commission. However, these concentrations can be reduced to within the limits through use of some designs and modified operations. Tritium concentrations in the Next Generation Nuclear Plant using the SI process are significantly higher as calculated and are affected by parameters with large uncertainties (i.e., tritium permeability of the process heat exchanger, the hydrogen concentration in the heat transfer and process fluids, the equilibrium constant of the isotope exchange reaction between HT and H 2 SO 4 ). These parameters, including tritium generation and the release rate in the reactor core, should be more accurately estimated in the near future to improve the calculations for the NGNP using the SI process. Decreasing the tritium permeation through the heat exchanger between the primary and secondary circuits may be an an effective measure for decreasing tritium concentrations in the hydrogen product, the hydrogen plant, and the tertiary coolant.iv v EXECUTIVE SUMMARYThis study evaluated tritium concentrations in the hydrogen product and in process chemicals in the energy transport systems and the hydrogen plant associated with the Next Generation Nuclear Plant (NGNP). In this work, tritium generation and transport mechansisms in the NGNP are described. The mathematics of these mechanisms are outlined, and are then codified and analyzed using a Japan Atomic Energy Agency (JAEA) analysis code called THYTAN [Tritium and HYdrogen Transportation ANalysis code ]. As a preliminary step, the THYTAN code was benchmarked against data available from the Peach Bottom HTGR. After benchmarking, various configurations of the NGNP employing a hightemperature electrolysis (HTE) hydrogen plant and an NGNP employing a Sulfur-Iodine (SI) hydrogen plant were analyzed, and the concentrations of tritium in the process and product streams were compared to current regulatory effluent limits in ground water and in air.Tritium is generated in the core of the reactor from the ternary fission of nuclear fuel (e.g., e.g., 233 B. Tritium from these reactions diffuses from the core materials into the primary coolant, where it can migrate to other parts of the system through bulk transport, diffusion, and isotope exchange mechanisms. Tritium is lost from the system when it diffuses through barrier materials to the outside environ...

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Operating history report for the Peach Bottom HTGR. Volume I. Reactor operating history

Cited by 5 publications

References 0 publications

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Nuclear powered CO₂ capture from the atmosphere

Tritium Movement and Accumulation in the NGNP System Interface and Hydrogen Plant

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Operating history report for the Peach Bottom HTGR. Volume I. Reactor operating history

Cited by 5 publications

References 0 publications

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Preliminary Failure Modes and Effects Analysis of the US Massive Gas Injection Disruption Mitigation System Design

Nuclear powered CO2 capture from the atmosphere

Tritium Movement and Accumulation in the NGNP System Interface and Hydrogen Plant

Contact Info

Product

Resources

About

Nuclear powered CO₂ capture from the atmosphere