Published 1995 | Version v1
Book

Disposal of long-lived spent fuel - A well controlled waste stream in our society

Creators

  • 1. Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

Description

The nuclear fuel cycle and its radioactive wastes has played a key role in the nuclear power development and debate for decades. This is true, particularly regarding questions related to disposal of spent fuel and other-lived waste. Most of the long lived waste existing today is fuel used in the reactors. The main part is stored at the reactors sites and normally in water pools or on increasing scale in dry storage containers. Large quantities have also been reprocessed or are stored at reprocessing plants or in long term interim storage facilities. There is in general no urgent need for final disposal of the high level long lived wastes, neither the fuel nor the vitrified wastes. A long interim storage period will facilitate a permanent solution for both categories as radioactivity and heat generation decays. The overall objective of radioactive waste management is to achieve a process within the whole nuclear fuel cycle that well protects man and environment from being harmed. The process should as much as possible limit burdens on future generations by for example reducing the quantities of wastes, minimize environmental impact, encourage efficient utilization of energy resources and keep various options open. Much of this can be met with today's technology and existing knowledge, planning, and regulations which together will guarantee a very safe handling and disposal as long as the waste management is carried out in a correct and well controlled way. The most important goal for safety is, however, -for all kinds of wastes- to keep them well isolated for the first one thousand years and during the relatively short time needed for fission products as cesium and strontium to decay. There exists a well founded international consensus that an isolation system based on geological disposal and use of a multi barrier system could form a very appropriate and technically simple method to achieve robust isolation with large safety margins. (O.M.)

Part of:
Global 1995

Additional details

Additional titles

Original title (English)
Global 1995

Publishing Information

Publisher
Edition ANS
Imprint Place
Paris (France)
Imprint Title
Global 1995
Imprint Pagination
2032 p.
Journal Page Range
p. 88-93

Conference

Title
International conference on evaluation of emerging nuclear fuel cycle systems
Dates
11-14 Sep 1995
Place
Versailles (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
29062058
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CYCLE; RADIOACTIVE WASTE DISPOSAL; SPENT FUELS; YEARS LIVING RADIOISOTOPES
Descriptors DEC
ENERGY SOURCES; FUELS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEAR FUELS; RADIOISOTOPES; REACTOR MATERIALS; WASTE DISPOSAL; WASTE MANAGEMENT

Optional Information

Notes
Imprint:Global 1995