Published March 1989 | Version v1
Report

Radionuclide characterization of reactor decommissioning waste and spent fuel assembly hardware

  • 1. Pacific Northwest Lab., Richland, WA (USA)

Description

The US Nuclear Regulatory Commission (NRC) has recently enacted rules setting forth technical, safety, and financial criteria for decommissioning of licensed nuclear facilities, including commercial nuclear power stations. These rules have addressed six major issues, including decommissioning alternatives, timing, planning, financial assurance, residual radioactivity, and environmental review. Also, the rules governing disposal of low-level radioactive wastes in commercial shallow land burial facilities will be applicable to most of the wastes generated during reactor decommissioning. This study has been implemented to provide the NRC and licensees with a more comprehensive and defensible data base and regulatory assessment of the radiological factors associated with reactor decommissioning and disposal of wastes generated during these activities. The objectives of this study are being accomplished during a two-phase sampling, measurement, and appraisal program utilizing: (1) the decommissioning of Shippingport Atomic Power Station, and (2) neutron activated materials from commercial reactors. Radioactive materials obtained from Shippingport Station and from a number of commercial stations for comprehensive radionuclide and stable element analyses are being utilized to assess the following important aspects of reactor decommissioning and radioactive waste characterization: (1) radiological safety and technology assessment from an actual reactor decommissioning (Shippingport); (2) radiological characterization of intensely radioactive materials (greater than Class-C) associated with the reactor pressure vessel and spent fuel assembly hardware from commercial nuclear power plants; (3) evaluation of the accuracy of computer codes for predicting radionuclide inventories in retired reactors and neutron activated components; and (4) assessment of waste disposal options associated with reactor decommissioning

Additional details

Publishing Information

Imprint Title
Sixteenth water reactor safety information meeting. Volume 1: Plenary session, Decontamination and decommissioning, License renewal, Human factors, generic issues, Risk analysis/PRA applications, Innovative concepts for increased safety of advanced power reactors
Imprint Pagination
561 p.
Journal Page Range
p. 73-118.
Report number
NUREG/CP--0097-Vol.1

Conference

Title
16. water reactor safety information meeting.
Dates
24-27 Oct 1988.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21014145
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; ACTIVITY LEVELS; BIOLOGICAL SHIELDS; BWR TYPE REACTORS; COMPUTER CODES; CONCRETES; DECONTAMINATION; EMISSION SPECTROSCOPY; ENVIRONMENTAL IMPACTS; FINANCING; FUEL ASSEMBLIES; FUEL ASSEMBLY DISMANTLING; INCONEL ALLOYS; MECHANICAL STRUCTURES; ORGANIZING; PIPES; PLANNING; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RADIOACTIVE WASTES; RADIOISOTOPES; RADIOMETRIC ANALYSIS; REACTOR COMPONENTS; REACTOR CORES; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; REACTOR MATERIALS; REACTOR SAFETY; RELIABILITY; SECONDARY COOLANT CIRCUITS; SHIPPINGPORT REACTOR; SPACERS; SPENT FUELS; STAINLESS STEELS; US NRC; WASTE MANAGEMENT; ZIRCALOY
Descriptors DEC
ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; CHEMICAL ANALYSIS; CLEANING; CONTAINERS; COOLING SYSTEMS; DECOMMISSIONING; DEMOLITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MANAGEMENT; MATERIALS; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NUCLEAR FUELS; POWER REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SHIELDS; SPECTROSCOPY; STEELS; THERMAL REACTORS; US ORGANIZATIONS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Secondary number(s)
CONF-8810155--Vol.1.