Interim guidance for the safe transport of

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Transcription:

IAEA-TECDOC-750 Interim guidance for the safe transport of reprocessed uranium INTERNATIONAL ATOMIC ENERGY AGENCY

The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse

Increasingly reprocessed uranium FOREWORD

EDITORIAL NOTE In preparing this document for press, staff of the IAEA have made up the pages from the original manuscript(s).

CONTENTS 1. INTRODUCTION...

APPENDIX

Application 1. INTRODUCTION

TABLE I. THE PHYSICAL PROPERTIES OF REPROCESSED URANIUM Chemical form (molecular formula) Physical state during transport Soluble/ insoluble Fractional uranium content (w/w) Uranium trioxide U0 3 solid moderately soluble U/U0 3 0,832 Uranyl nitrate U0 2 (N0 3 ) 2 solid/liquid soluble U/UO 2 (NO 3 ) 2.nH 2 O 0.474 a Uranium tetra-fluoride solid moderately soluble U/UF 4 0.758 UF 4 Uranium hexafluoride solid soluble U/UF 6 0.676 UF 6 Uranyl fluoride U0 2 F 2 solid soluble U/U0 2 F 2 0.773 Uranium dioxide UO 2 solid insoluble U/UO 2 0.881 Tri-uranium octoxide U 3 0 8 solid insoluble U/U 3 O 8 0.848 a Generally, the water of crystallization in the solid is n = 6, and so the uranium content is 0.474 in that form.

3. DEFINITION OF UNIRRADIATED URANIUM

4.2.2. Reprocessed uranium classified as LSA-II LSA-II is defined as follows in the current Regulations: "131. Low specific activity (LSA) material shall mean radioactive material which by

surrounding

transport

is primarily because

Package inspection to the requirements specified in para. 402 of the Regulations should

5. SUMMARY The consultants services meetings have examined the transport of reprocessed uranium

(b) When 10 mg of reprocessed uranium material contains in radioactivity less than

Appendix

Appendix II NUCLIDES COMPOSING REPROCESSED URANIUM Uranium compounds such as UF

to TABLE IV. CHARACTERISTICS OF REPROCESSED URANIUM PACKAGE Enriched uranium of natural source Enrichment A 2 (Bq) Item U 5% Unlimited Quantity equivalent of A 2 (kg) Activity (Bq/g) Activity limit of LSA-II (10%/B) Activity limit of LSA-III (2 X 10' 3 A 2 /g) Unlimited

Appendix in IAEA REGULATIONS CONCERNING REPROCESSED URANIUM This appendix summarizes those standards specified

Appendix

(2) UK proposal: Pu, FP, 236 U Whilst chemical purification techniques

Attachment

PROBLEMS Attachment 2 to Appendix IV

lower specific activity than

Appendix V REPROCESSED URANIUM CLASSIFIED AS LSA-II Reprocessed uranium can be classified as LSA-II in the following cases:

"AI.4.3.

TABLE

Appendix

(U) Samples U0 2, U 3 0 8 powder U(%), O/U 3, F(ppm),

TABLE VIII. LEACHING TEST RESULTS

Attachment

Attachment

TREATMENT Appendix VII

requires further regulation under LSA-III

Appendix VIII A 2 OF MIXTURE TABLE IX. EXAMPLE OF CALCULATING A 2 VALUE (MIXTURE) 3 Uranium isotopes Content ratio of reprocessed uranium az U 234 u 235JJ 236 U Z38JJ Z28 Th

A Appendix IX

ê TABLE X. THE RELATION BETWEEN URANIUM ENRICHMENT AND A 2 VALUES Uranium isotopes A 2 (i) [Bq] 232 U 3 x 10 s 228 Th< 234 U 235 U 236 U 238 U "Tc Total A 2 value Remarks

TABLE

Appendix

TABLE XIII. EXTENT OF CONTRIBUTION OF RADIOACTIVE IMPURITIES AS A WHOLE TO THE VALUE OF A 2 (TEST CALCULATION WITH ENRICHED REPROCESSED URANIUM) (a) All nuclides taken into account Nuicl ides a o^

(b) Only representative nucl ides evaluated

DAUGHTER NUCLIDES Appendix XI

TABLE

Appendix XII CLASSIFICATION OF AN EMPTY CYLINDER CONTAINING UF

Since the specific activity under 1 is greater than that under 2 the transported item does not satisfy the standard for LSA-II. Alternatively, to qualify for a Type A transport, the total activity must

INVESTIGATIONS Annex

Abstract The

2. MODELLING FOR APPLYING THE ISOSHLD-PROGRAMME

FIG.

TABLE

1000 f 100 As

10000 1000 100 1 year 4 years 10.23 years 16 years FIG.

O) u crö 20 nsv/h SO 50 25 lisv/h distance

Öl o crö +-> i/l "O FIG. 13. Vector l, container drained, time: 1 year. FIG. 14. Vector 2, container drained, time: 10.23 years. 69

FIG.

10000 vector! vector 2 vector 3 vector 4 FIG.

10000 vector 1 vector 2 vectors vector 4 FIG. 19. Comparison of surface dose rates of the drained container after 10.23 years. 72

REFERENCES [1] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Material, Safety Series No. 6, 1985 Edition (As Amended 1990), IAEA, Vienna (1990). [2] INTERNATIONAL ATOMIC ENERGY AGENCY, Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition), Second Edition (As Amended 1990), Safety Series No. 7, IAEA, Vienna (1990).

CONTRIBUTORS TO DRAFTING AND REVIEW Consultants Services Meeting, Vienna,