A safeguards concept for the AVR fuel element storage areas at the KFA Jülich
A safeguards concept for the AVR fuel element storage areas at the KFA Jülich
Although the KFA-Jülich has been subject to international inspection under the Euratom Treaty from the outset, safeguards measures for special nuclear material are currently being re-negotiated and reorganized to correspond to the new and more stringent requirements laid down in the Verification Agr...
Saved in:
Personal Name(s): | Canty, M. J. |
---|---|
Buttler, R. | |
Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich, Zentralbiliothek, Verlag
1980
|
Physical Description: |
39 p., 10 fig. |
Document Type: |
Report Book |
Research Program: |
ohne Topic |
Series Title: |
Berichte der Kernforschungsanlage Jülich
1687 |
Link: |
OpenAccess |
Publikationsportal JuSER |
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100 | 1 | |a Canty, M. J. |0 P:(DE-HGF)0 |b 0 | |
245 | |a A safeguards concept for the AVR fuel element storage areas at the KFA Jülich | ||
260 | |a Jülich |c 1980 |b Kernforschungsanlage Jülich, Zentralbiliothek, Verlag | ||
300 | |a 39 p., 10 fig. | ||
490 | 0 | |a Berichte der Kernforschungsanlage Jülich |v 1687 | |
520 | |a Although the KFA-Jülich has been subject to international inspection under the Euratom Treaty from the outset, safeguards measures for special nuclear material are currently being re-negotiated and reorganized to correspond to the new and more stringent requirements laid down in the Verification Agreement pursuant to the Nuclear Weapons Nah-Proliferation Treaty (NPT). Nuclear research centres in general pose special problems for international nuclear material control. The total amount of material present isusually distributed over a multitude of individual items and batches. The classical IAEA safeguards measure of periodic MUF (material unaccounted for) determination is impractical. A viable alternative approach is to focus attention only an those few classes of physical inventory which contain the bulk of the fissile material. Such classes at the KFA Jülich comprise the frech and irradiated fuel assemblies for the two research reactors FRJ-1 and FRJ-2, fuel pebbles for the KAHTER critical assembly and stored spent AVR fuel. We will be concerned in the present investigation with developing a safeguards concept for the spent AVR fuel. A large fraction of the total inventory of fissile material at the KFA-Jülich is in the form of irradiated fuel from the AVR high temperature reactor. This material is accessible to measurement for verification purposes only with considerable difficulty and therefore poses serious technical problems from a safeguards standpoint. With the continuing operation of the AVR, coupled with still unresolved problems of final disposal, theamount of material in this category is increasing steadily. Moreover it is expected that the AVR pebbles will merge with irradiated fuel from the THTR-3oo in a large HTR away-fromareactor dry storage installation, also located at the KFA, thus becoming part of a much larger inventory of fissile material. With the gradual decay of short-lived fission products, its potential strategic value will increase steadily, rendering adequate safeguards measures indispensable. In this report the operation of present AVR spent [...] | ||
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