Candidate materials performance under Supercritical Water Reactor (SCWR) conditions

Aki Toivonen, Sami Penttilä, Laura Rissanen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Abstract

The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.
Original languageEnglish
Title of host publicationBaltica VIII
Subtitle of host publicationLife Management and Maintenance for Power Plants
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages351-371
Volume1
ISBN (Electronic)978-951-38-7592-3
ISBN (Print)978-951-38-7591-6
Publication statusPublished - 2010
MoE publication typeB3 Non-refereed article in conference proceedings
EventBALTICA VIII - International Conference on Life Management and Maintenance for Power Plants - Helsinki-Stockholm, Finland
Duration: 18 May 201020 May 2010

Publication series

SeriesVTT Symposium
Number264
ISSN0357-9387

Conference

ConferenceBALTICA VIII - International Conference on Life Management and Maintenance for Power Plants
CountryFinland
CityHelsinki-Stockholm
Period18/05/1020/05/10

Fingerprint

Austenitic steel
Stress corrosion cracking
Creep
Oxidation resistance
Oxides
Chromium
Corrosion
Water
Creep resistance
Light water reactors
Reactor cores
Iron alloys
Nickel alloys
Alloy steel
Austenitic stainless steel
Joining
Coolants
Strain rate
Nickel
Coal

Cite this

Toivonen, A., Penttilä, S., & Rissanen, L. (2010). Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. In Baltica VIII: Life Management and Maintenance for Power Plants (Vol. 1, pp. 351-371). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 264
Toivonen, Aki ; Penttilä, Sami ; Rissanen, Laura. / Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1 Espoo : VTT Technical Research Centre of Finland, 2010. pp. 351-371 (VTT Symposium; No. 264).
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Toivonen, A, Penttilä, S & Rissanen, L 2010, Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. in Baltica VIII: Life Management and Maintenance for Power Plants. vol. 1, VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 264, pp. 351-371, BALTICA VIII - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 18/05/10.

Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. / Toivonen, Aki; Penttilä, Sami; Rissanen, Laura.

Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1 Espoo : VTT Technical Research Centre of Finland, 2010. p. 351-371 (VTT Symposium; No. 264).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

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T1 - Candidate materials performance under Supercritical Water Reactor (SCWR) conditions

AU - Toivonen, Aki

AU - Penttilä, Sami

AU - Rissanen, Laura

PY - 2010

Y1 - 2010

N2 - The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.

AB - The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.

M3 - Conference article in proceedings

SN - 978-951-38-7591-6

VL - 1

T3 - VTT Symposium

SP - 351

EP - 371

BT - Baltica VIII

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Toivonen A, Penttilä S, Rissanen L. Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. In Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1. Espoo: VTT Technical Research Centre of Finland. 2010. p. 351-371. (VTT Symposium; No. 264).