APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

C. P.C. Wong; S. Malang; M. Sawan; I. Sviatoslavsky; E. Mogahed; S. Smolentsev; S. Majumdar; B. Merrill; R. Mattas; M. Friend; J. Bolin; S. Sharafat

doi:10.1016/j.jnucmat.2004.04.348

APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

C. P.C. Wong, S. Malang, M. Sawan, I. Sviatoslavsky, E. Mogahed, S. Smolentsev, S. Majumdar, B. Merrill, R. Mattas, M. Friend, J. Bolin, S. Sharafat

Research output: Contribution to journal › Conference article › peer-review

5 Scopus citations

Abstract

As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m², and a maximum neutron wall loading of 5.4 MW/m², with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.

Original language	English
Pages (from-to)	1599-1604
Number of pages	6
Journal	Journal of Nuclear Materials
Volume	329-333
Issue number	1-3 PART B
DOIs	https://doi.org/10.1016/j.jnucmat.2004.04.348
State	Published - Aug 1 2004
Externally published	Yes
Event	Proceedings of the 11th Conference on Fusion Research - Kyoto, Japan Duration: Dec 7 2003 → Dec 12 2003

Funding

This report of work was supported by the US Department of Energy under Contract No. DE-AC03-98ER54411.

Funders	Funder number
US Department of Energy

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1016/j.jnucmat.2004.04.348

Cite this

@article{6d3f3dad15204a7795528c04bca402a1,

title = "APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design",

abstract = "As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m2, and a maximum neutron wall loading of 5.4 MW/m2, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.",

author = "Wong, {C. P.C.} and S. Malang and M. Sawan and I. Sviatoslavsky and E. Mogahed and S. Smolentsev and S. Majumdar and B. Merrill and R. Mattas and M. Friend and J. Bolin and S. Sharafat",

year = "2004",

month = aug,

day = "1",

doi = "10.1016/j.jnucmat.2004.04.348",

language = "English",

volume = "329-333",

pages = "1599--1604",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "1-3 PART B",

note = "Proceedings of the 11th Conference on Fusion Research ; Conference date: 07-12-2003 Through 12-12-2003",

}

TY - JOUR

T1 - APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

AU - Wong, C. P.C.

AU - Malang, S.

AU - Sawan, M.

AU - Sviatoslavsky, I.

AU - Mogahed, E.

AU - Smolentsev, S.

AU - Majumdar, S.

AU - Merrill, B.

AU - Mattas, R.

AU - Friend, M.

AU - Bolin, J.

AU - Sharafat, S.

PY - 2004/8/1

Y1 - 2004/8/1

N2 - As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m2, and a maximum neutron wall loading of 5.4 MW/m2, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.

AB - As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m2, and a maximum neutron wall loading of 5.4 MW/m2, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.

UR - http://www.scopus.com/inward/record.url?scp=3342961627&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2004.04.348

DO - 10.1016/j.jnucmat.2004.04.348

M3 - Conference article

AN - SCOPUS:3342961627

SN - 0022-3115

VL - 329-333

SP - 1599

EP - 1604

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 PART B

T2 - Proceedings of the 11th Conference on Fusion Research

Y2 - 7 December 2003 through 12 December 2003

ER -

APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

Abstract

Funding

UN SDGs

Access to Document

Other files and links

Fingerprint

Cite this