Published November 1999 | Version v1
Journal article

Department of Energy's annealing prototype demonstration projects

  • 1. Department of Energy, Washington, DC (United States)
  • 2. Sandia National Laboratories, Albuquerque, NM (United States)

Description

One of the challenges utilities face in addressing technical issues associated with the aging of nuclear power plants is the long-term effect of plant operation on reactor pressure vessels. These vessels are exposed to neutrons during the operation of a reactor. For certain plants, this exposure can cause embrittlement of some of the vessel welds, which can shorten the useful life of the vessel. This reactor pressure vessel embrittlement issue has the potential to affect the continued operation of a number of US pressurized water reactor plants. However, the properties that are degraded by long-term irradiation can be recovered through a thermal annealing treatment of the vessel steel. Although a dozen Russian-designed and several US military vessels have been successfully annealed, US utilities concluded that an annealing demonstration using a US reactor pressure vessel was a prerequisite before annealing a licensed US nuclear power plant. In May 1995, the Department of Energy and Sandia National Laboratories initiated a program to evaluate the feasibility of annealing US licensed plants using two different heating technologies. One team completed its annealing prototype demonstration in July 1996, using an indirect gas-fired furnace at the uncompleted Public Service of Indiana's Marble Hill nuclear power plant in southern Indiana. The second team's annealing prototype demonstration using a direct heat electrical furnace at the uncompleted Consumers Power Company's nuclear power plant at Midland, Michigan, was scheduled to be completed in early 1997, but has now been delayed indefinitely. This paper describes the Department of Energy's annealing prototype demonstration program and the results to date for each project. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
194
Journal Issue
1
Journal Page Range
p. 7-18
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
24. water reactor safety information meeting (WRSM-24)
Dates
21-23 Oct 1996
Place
Bethesda, MD (United States)

INIS

Country of Publication
Netherlands
Country of Input or Organization
Switzerland
INIS RN
31008650
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANNEALING; EMBRITTLEMENT; FURNACES; NEUTRONS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; RADIATION EFFECTS; REACTOR SAFETY; TEST FACILITIES
Descriptors DEC
BARYONS; CONTAINERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HEAT TREATMENTS; NUCLEAR FACILITIES; NUCLEONS; POWER PLANTS; SAFETY; THERMAL POWER PLANTS

Optional Information

Notes
4 refs.