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Title: Safeguards techniques in a pilot conditioning plant for spent fuel

Abstract

The pilot conditioning plant at Gorleben, Germany, is designed as a multi-purpose plant. Its primary task is the conditioning of spent fuel assemblies into a form suitable for final disposal. As a pilot plant, it allows furthermore for the development and testing of various conditioning techniques. In terms of international safeguards, the pilot conditioning plant is basically considered an item facility. Entire fuel assemblies enter the plant in transport casks, whereas bins filled with fuel rods or canisters containing cut fuel rods leave the facility in final disposal packages (e.g. POLLUX). Each POLLUX final disposal package content is uniquely correlated to a definite number of fuel assemblies which have entered the conditioning process. For this type of facility, containment/surveillance (C/S) should take over the major role in nuclear material safeguards. This paper discusses the safeguards at the Gorleben plant.

Authors:
; ;  [1]
  1. (GNS, Hannover (DE))
Publication Date:
OSTI Identifier:
5516544
Report Number(s):
CONF-910774--
Journal ID: ISSN 0362-0034; CODEN: NUMMB
Resource Type:
Conference
Resource Relation:
Journal Name: Nuclear Materials Management. Annual Meeting Proceedings; (United States); Journal Volume: 20; Conference: 32. Institute of Nuclear Materials Management (INMM) annual meeting, New Orleans, LA (United States), 28-31 Jul 1991
Country of Publication:
United States
Language:
English
Subject:
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; FUEL ASSEMBLIES; NUCLEAR SAFETY PILOT PLANT; SPENT FUELS; CONTAINMENT; GERMANY; INTERNATIONAL AGREEMENTS; SAFEGUARDS; SURVEILLANCE; AGREEMENTS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTOR SAFETY EXPERIMENTS 055000* -- Nuclear Fuels-- Safeguards, Inspection, & Accountability; 220900 -- Nuclear Reactor Technology-- Reactor Safety; 050800 -- Nuclear Fuels-- Spent Fuels Reprocessing

Citation Formats

Leitner, E., Rudolf, K., and Weh, R. Safeguards techniques in a pilot conditioning plant for spent fuel. United States: N. p., 1991. Web.
Leitner, E., Rudolf, K., & Weh, R. Safeguards techniques in a pilot conditioning plant for spent fuel. United States.
Leitner, E., Rudolf, K., and Weh, R. 1991. "Safeguards techniques in a pilot conditioning plant for spent fuel". United States. doi:.
@article{osti_5516544,
title = {Safeguards techniques in a pilot conditioning plant for spent fuel},
author = {Leitner, E. and Rudolf, K. and Weh, R.},
abstractNote = {The pilot conditioning plant at Gorleben, Germany, is designed as a multi-purpose plant. Its primary task is the conditioning of spent fuel assemblies into a form suitable for final disposal. As a pilot plant, it allows furthermore for the development and testing of various conditioning techniques. In terms of international safeguards, the pilot conditioning plant is basically considered an item facility. Entire fuel assemblies enter the plant in transport casks, whereas bins filled with fuel rods or canisters containing cut fuel rods leave the facility in final disposal packages (e.g. POLLUX). Each POLLUX final disposal package content is uniquely correlated to a definite number of fuel assemblies which have entered the conditioning process. For this type of facility, containment/surveillance (C/S) should take over the major role in nuclear material safeguards. This paper discusses the safeguards at the Gorleben plant.},
doi = {},
journal = {Nuclear Materials Management. Annual Meeting Proceedings; (United States)},
number = ,
volume = 20,
place = {United States},
year = 1991,
month = 1
}

Conference:
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  • The advanced spent fuel conditioning process (ACP) which is a part of a pyro-processing has been under development at Korean Atomic Energy Research Institute (KAERI) since 1997 to tackle the problem of an accumulation of spent fuel. The concept is to convert spent oxide fuel into a metallic form in a high temperature molten salt in order to reduce the heat energy, volume, and radioactivity of a spent fuel. Since the inactive tests of the ACP have been successfully implemented to confirm the validity of the electrolytic reduction technology, a lab-scale hot test will be undertaken in a couple ofmore » years to validate the concept. For this purpose, the KAERI has built the ACP Facility (ACPF) at the basement of the Irradiated Material Examination Facility (IMEF) of KAERI, which already has a reserved hot-cell area. Through the bilateral arrangement between US Department of Energy (DOE) and Korean Ministry of Science and Technology (MOST) for safeguards R and D, the KAERI has developed elements of safeguards system for the ACPF in cooperation with the Los Alamos National Laboratory (LANL). The reference safeguards design conditions and equipment were established for the ACPF. The ACPF safeguards system has many unique design specifications because of the particular characteristics of the pyro-process materials and the restrictions during a facility operation. For the material accounting system, a set of remote operation and maintenance concepts has been introduced for a non-destructive assay (NDA) system. The IAEA has proposed a safeguards approach to the ACPF for the different operational phases. Safeguards measures at the ACPF will be implemented during all operational phases which include a 'Cold Test', a 'Hot Test' and at the end of a 'Hot test'. Optimization of the IAEA's inspection efforts was addressed by designing an effective safeguards approach that relies on, inter alia, remote monitoring using cameras, installed NDA instrumentation, gate monitors and seals. This paper addresses the main features of the ACP safeguards development status and the future prospects of safeguards implementation at the ACPF, KAERI-Daejeon. It is expected that deployment of these advanced safeguards technologies would be useful for a pyro-processing facility. (authors)« less
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  • In the Federal Republic of Germany the first facility for dry storage of spent fuel is ready for operation and some more facilities will be available in the near future. Since, according to German law, spent fuel is to be reprocessed, these facilities are interim stores and designed accordingly. In the present paper a facility with 1500 t heavy metal storage capacity and transport/storage casks under consideration are described. This type of nuclear facility is new with regard to international safeguards, therefore attention is given to safeguards related aspects. Main topics are the necessary inclusion of safeguards procedures in shippingmore » facilities, a scheme for indirect verification of transport cask contents and the extraordinarily important role of containment/surveillance measures.« less