Published 1988 | Version v1
Miscellaneous Metadata-only

Study on 2 1/4 Cr-1 Mo steel for high temperature gas-cooled reactor - material characterization of forged low Si 2 1/4 Cr-1 Mo steel

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Material Strength Lab.
  • 2. Japan Atomic Energy Research Inst., Tokyo (Japan). Office of Planning
  • 3. Japan Steel Works Ltd., Muroran, Hokkaido (Japan). Muroran Research Lab.
  • 4. Japan Steel Works Ltd., Muroran, Hokkaido. Muroran Plant

Description

As a result of research and development works of HTGR by JAERI, the high temperature engineering test reactor (HTTR) is expected to be constructed in the near future. As the reactor pressure vessel (RPV) material, 2 1/4 Cr-1 Mo steel will be used. Material characterization test has been carried out to evaluate the applicability of the 2 1/4 Cr-1 Mo steel to the RPV and to prepare for the licensing. The present paper summarizes the fracture toughness behavior including KId and KIa, irradiation embrittlement susceptibility and degradation of steel due to the long term aging at high temperature of the forged low Si 2 1/4 Cr-1 Mo steel. These tests reveal good fracture toughness which well meets the requirements of the ASME Code, low neutron irradiation embrittlement susceptibility, little embrittlement by long term aging and so on. The test results demonstrate good applicability to the RPV of HTGR. (orig./DG)

Availability note (English)

Available from Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt.

Additional details

Additional titles

Original title (no language)
Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt 'Langzeitintegritaet der druckfuehrenden Bauteile von Kernkraftwerken'. Bd. 1 und 2.

Publishing Information

Imprint Title
Safety and reliability of plant technology with special emphasis on long-term integrity of pressure components of nuclear power plants. Vol. 1 and 2
Imprint Pagination
1003 p.
Journal Page Range
p. 35.1-35.20.

Conference

Title
Long-term integrity of pressure components of nuclear power plants.
Original Conference Title
14. MPA-Seminar ueber Sicherheit und Verfuegbarkeit in der Anlagentechnik: Langzeitintegritaet der Druckfuehrenden Bauteile von Kernkraftwerken
Acronym
14. MPA-seminar on safety and reliability of plant technology
Dates
6-7 Oct 1988.
Place
Stuttgart (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
21013492
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
EMBRITTLEMENT; FRACTURE PROPERTIES; HTGR TYPE REACTORS; IRRADIATION; LOW ALLOY STEELS; PRESSURE VESSELS; VERY HIGH TEMPERATURE
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; REACTORS; STEELS

Optional Information

Notes
Imprint:Published in 2 separate volumes.;Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt 'Langzeitintegritaet der druckfuehrenden Bauteile von Kernkraftwerken'. Bd. 1 und 2.;Bd. 1: Anlagentechnik, Thermoschock, strahleninduzierte Versproedung, Korrosion/Verschleiss, zerstoerungsfreie Pruefung. Bd. 2: Zeitstandverhalten/Kriechvorgaenge, Behaelter- und Komponenten-Integritaet, Rohrleitungsverhalten.