Verification and validation of TMAP4

Longhurst, G.R.; Harms, S.L.; Marwil, E.S.; Miller, Barry G.

doi:10.2172/7026318

Cited by 8 publications

(9 citation statements)

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“…There are numerous publications citing instances where the codes and fit parameters have been used to simulate experiments. References [875,889,901,904,[909][910][911][912][913][914][915][916][917] are representative.…”

Section: Status Of Model Validationmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Status Of Model Validationmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…PARFUME allows simulation of fission product (FP) transport from individual TRISO-coated fuel particles to the surrounding graphite and from the surrounding graphite to a release from the fuel element. These capabilities are based on portions of existing coding extracted from the Tritium Migration Analysis Program, TMAP4 40,41 and adapted to run within PARFUME. Additionally, development is underway on an analytical diffusion model.…”

Section: Fission Product Diffusion Modelsmentioning

confidence: 99%

PARFUME Theory and Model basis Report

Miller¹,

Petti²,

Maki³

et al. 2009

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The success of gas reactors depends upon the safety and quality of the coated particle fuel. The fuel performance modeling code PARFUME simulates the mechanical, thermal and physico-chemical behavior of fuel particles during irradiation. This report documents the theory and material properties behind various capabilities of the code, which include: 1) various options for calculating CO production and fission product gas release, 2) an analytical solution for stresses in the coating layers that accounts for irradiation-induced creep and swelling of the pyrocarbon layers, 3) a thermal model that calculates a time-dependent temperature profile through a pebble bed sphere or a prismatic block core, as well as through the layers of each analyzed particle, 4) simulation of multi-dimensional particle behavior associated with cracking in the IPyC layer, partial debonding of the IPyC from the SiC, particle asphericity, and kernel migration (or amoeba effect), 5) two independent methods for determining particle failure probabilities, 6) a model for calculating release-to-birth ratios of gaseous fission products that accounts for particle failures and uranium contamination in the fuel matrix, and 7)

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“…The variance falls below 0.2 % at time, t = 34 sec. The value is initially high because of the division by a small number in Equation (6). The comparisons for this problem are listed in Table 16.…”

Section: Gives the Concentrations Of [A] And [B] Asmentioning

confidence: 99%

Verification and Validation of TMAP7

Ambrosek¹

2005

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The Tritium Migration Analysis Program, Version 7 (TMAP7) code is an update of TMAP4, an earlier version that was verified and validated in support of the International Thermonuclear Experimental Reactor (ITER) program and of the intermediate version TMAP2000. It has undergone several revisions. The current one includes radioactive decay, multiple trap capability, more realistic treatment of heteronuclear molecular formation at surfaces, processes that involve surface-only species, and a number of other improvements. Prior to code utilization, it needed to be verified and validated to ensure that the code is performing as it was intended and that its predictions are consistent with physical reality. To that end, the demonstration and comparison problems cited here show that the code results agree with analytical solutions for select problems where analytical solutions are straightforward or with results from other verified and validated codes, and that actual experimental results can be accurately replicated using reasonable models with this code. These results and their documentation in this report are necessary steps in the qualification of TMAP7 for its intended service. This revision updates results using TMAP7.1, which corrected some code deficiencies found in TMAP7.iv v CONTENTS

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Verification and validation of TMAP4

Cited by 8 publications

References 1 publication

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

PARFUME Theory and Model basis Report

Verification and Validation of TMAP7

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