ML22277A792
| ML22277A792 | |
| Person / Time | |
|---|---|
| Site: | 07103097 |
| Issue date: | 08/03/2022 |
| From: | Boyle R, Shaw D TN Americas LLC |
| To: | Division of Fuel Management |
| Garcia-Santos N | |
| Shared Package | |
| ML22277A716 | List:
|
| References | |
| EPID L-2022-DOT-0008, CAC A33010 | |
| Download: ML22277A792 (33) | |
Text
Unrestricted Orano 0
Orano NPS SAFETY ANALYSIS CHAPTER 1.3 REPORT SPECIFICATIONS RELATING TO RADIOACTIVE CONTENT Formulaire : PM04-4-MO-6 rév. 03 orano Prepared by FCC4 Checked by Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 1 / 33 Table of contents Status of revision 2 Brand names 2
- 1. Purpose 3
- 2. Description of the Content 3
- 3. Thermal power 5
- 4. Activity 6
- 5. Definition of maximum radioactive contents 9
- 6. Conclusion 9
- 7. References 9 List of figures 10 List of tables 11 List of appendices 12 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 2 of 33 Status of revision English French I
Date Purpose and record of revisions Prepared by / Verified by version version Old reference: DOS-13-00081778-030 Initial issue:
- Merging and updates to the following documents: Paragraph 2 of summary note TFXDC 2158 Rev. H and document FFDC05083 Rev. B
- Information added relating to replacement rods
- ERU isotope spectrum updated with U234 increased from 0.25 % to 0.3 %
and U236 increased from 3.2 % to 4 %.
I 0 0 04/2012
- Limited values of A2 taken into account for Enriched Natural Uranium (ENU)
- Fission products taken into account in activity calculations I
- Verification of compliance with leaching criterion added
- Demonstration of compliance of the criterion relating to radiation intensity at 3 m.
- Analysis of the effect of ERU ageing
- Inclusion of the potential presence of a maximum of 5 g of glycerine on the fuel assemblies.
- Integration of Smooth-walled dummies and models of EPR' assemblies
- Integration of 17x17 GAIA 14-foot assemblies I 1 1 10/2016
- Addition of creep laws for M5 cladding
- Update of the mechanical properties of the fuel rod claddings
- Definition of maximum radioactive content
- Addition of authorisation for the presence of a desiccant New reference: DOS-19-021166-002
- Added possibility to define the package as type A I
1.0 1.0 02/2019 - Revised calculation of ENU activity § 4.2
- Corrected IAEA article § 4.3 and 4.5 I
- Update of the mechanical properties of the fuel rod cladding materials 2.0 04/2019
- Addition of creep law for Zircaloy-4 claddings
- Added possibility to have a Chrome coating thickness up to 30 µm on the 3.0 10/2020 zirconium alloy cladding.
2.0 - Addition of a note on Zr-4 and Zy-4 designations
- Correction of a unit error on the specific activity (A2/gU in place of A2/gUO2)
See 1st of ERU in section 4.6 4.0 page - Removal of IAEA section 601 in section 4.4
- Addition of the wedging description of non-assembled rods in rod box.
- Formal corrections Brand names AFA 3G, M5, Q12, MONOBLOC, TRAPPER, AGORA, HTP, HMP and ROBUST FUELGUARD are brands or registered brands of Framatome or its subsidiaries, in the USA or in other countries.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 3 of 33
- 1. Purpose The purpose of this document is to describe the radioactive content transported in the FCC4 packaging. Limitations in terms of activity and thermal power are analysed.
- 2. Description of the Content 2.1. Description of radioactive materials The following table describes the various radioactive materials authorized for transport in the FCC4 packaging model.
Characteristics of radioactive materials in the content Maximum thermal power emitted W (See section 3) per packaging
, for fuel containing ENU Emitted radiation
, , (the latter being the principal) for fuel containing ERU U 232 5,0.10-10 (g/gU)
U 234 5,5.10-4 (g/gU)
Isotopic vector of ENU per 1 g of U 235 5,0.10-2 (g/gU) uranium U 236 5,0.10-4 (g/gU)
U 238 balance U 232 5,0.10-8 (g/gU)
U 234 3,0.10-3 (g/gU)
Isotopic vector of ERU per 1 g of U 235 5,0.10-2 (g/gU) uranium U 236 4,0.10-2 (g/gU)
U 238 balance Sintered UO2 pellets and/or mix of UO2 and material acting Physical state and chemical form as neutron poison.
MaximumU235 enrichment 5%
Maximum density 100 % of UO2 theoretical density: 10.96 Special form No 2.2. Description of fuel assemblies The various types of fuel assembly to be transported differ either in the number and diameter of the fuel rods they contain, or in their length.
Detailed characteristics of the fuel assemblies to be transported, together with the corresponding weights, are given in Table 1.3-1.
The general composition of the assemblies, common to all types, is illustrated in Figures 1.3-1 to 1.3-5 and Figure 1.3-9. It comprises:
an inert supporting structure (skeleton) composed of zirconium alloy guide tubes (and an instrumentation tube for type 15x15 and 17x17 assemblies) fixed at their ends to 2 stainless steel nozzles. Zirconium alloy grids with a square-shaped honeycomb structure are arranged at regular intervals along the tubes. These act both as spacers for the tubes and as a restraining structure for the fuel rods. Some assemblies may be equipped with mid-span mixing grids (MSMG) which are additional to the support grids.
fuel rods, consisting of zirconium alloy claddings (receiving a plug at each end), filled with sintered UO2 pellets and/or a mixture of UO2 and a neutron poison material. This stack of pellets held in place by a compression spring constitutes the fissile column. The rods are pressurised with helium to a maximum absolute pressure of 32.7 bar at room temperature.
They are held in place by spacer grids within the fuel assembly.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 4 of 33 During transportation, the fuel assemblies may contain accessories referred to as "rod clusters" designed to facilitate the control of the nuclear reactions or of the heat exchanges in the reactor. These are illustrated in Figure 1.3-6. These rod clusters are made up of rods which insert into the guide tubes and are of 3 types:
RCCAs consisting either of absorber rods whose stainless steel claddings are filled with
() and (), or absorber rods containing and inert rods (stainless steel claddings containing stainless steel).
"poison" rod clusters which are "thimble plug" assemblies in which steel bars have been replaced by stainless steel claddings containing .
"inert" so-called "thimble plug" assemblies whose rods are stainless steel bars.
"primary source" rod clusters (without source rod) comprised of steel bars and for which the free location(s) are intended to accommodate the source rod(s) after unloading of the packagings.
When FCC4 Version 1 packagings hold a single fresh 17x17 EPR fuel assembly in a cluster configuration, it is possible to use ballasts to fill the empty cavity. Two ballast configurations are envisaged:
A model of the EPR assembly, comprising the same structural elements as an EPR fuel assembly (components, materials) unless it has tungsten carbide pellets in place of the fuel rod pellets. As a consequence, the characteristics of the model are identical to those presented in Table 1.3-1 for 17x17 EPR assemblies, with the exception of the characteristics of the fissile material.
A smooth-walled dummy assembly with radial spacers, as detailed in Figure 1.3 8. Its top nozzle has the same cross section as that of the EPR fuel assemblies. Its bottom nozzle has a reduced cross section of 210 mm x 210 mm as opposed to the 214 mm x 214 mm of an EPR fuel assembly. The uninterrupted section (external longitudinal body casing) has a cross section of 211.75 mm x 211.75 mm and is comprised of smooth faces (external face free of irregularities) made of austenitic stainless steel. The nominal length of the dummy is 4796 mm. The total mass of the smooth-wall dummy assembly and its radial spacers is 877 kg. All smooth-wall dummy assembly components are made of stainless steel.
In the case of incomplete fuel assemblies, the missing UO2 rods are replaced by gadolinium-bearing rods, rods containing depleted uranium or a metallic material, or even solid bars of metallic material (materials such as graphite and beryllium are strictly excluded). The presence of neutron poison in the metal bars is permitted. The pellets may contain chromium oxide.
Type 17x17 fuel assemblies may be transported with extra rods (additional fuel rods may be inserted into the guide-tubes).
A maximum of 5 g of glycerine may also be present in each of the assemblies or the assembly model.
2.3. Description of non-assembled rods Fuel rods are constituted of zirconium alloy tubular cladding (with a plug at both ends), filled with sintered UO2 uranium oxide pellets and/or sintered fuel pellets constituted by a mixture of UO2 and a neutron poison material. This stack of pellets, held in place by a compression spring, forms the fissile column (active length). The rods are pressurised with helium up to an absolute pressure of 32.7 bar maximum at room temperature. The characteristics of the rods are given in Table 1.3-2.
These non-assembled rods are grouped in FCC4 version rod boxes, as described in detail in Appendix 1.3-1, which are inserted in place of fuel assemblies in the FCC4 version 1 packagings. These FCC4 version rod boxes are designed for the transportation of 14-foot, 12-foot, 10-foot, 8-foot and EPR rod types. The rods are placed at the center of the rod box thanks to axial and radial wedges. The axial wedges are placed at the box ends and manually tightened in order to hold the rods axially. These wedges are fixed to the rod box with an Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 5 of 33 adjustable screw-nut system. Additional end plates are screwed on the axial wedges between rods and the axial wedge. For the radial wedging, the space above rods is filled by a system of support plates, radial wedges, and compensation wedges. The radial wedges, compensation wedges and support plates are held by the door pads.
The box is filled with full rows of rods. Where a row of fuel rods is incomplete, the row is made up with inert rods or solid stainless steel or Zirconium alloy bars having a nominal diameter between:
and mm for type 17x17 and 18x18 fuel rods, and mm for type 15x15, 14x14 and 16x16 fuel rods.
An outline drawing of the radial wedging is given in Figure 1.3-7. A detailed description of the rod box and wedging system for FCC4 rods and type EPR is given in Appendix 1.3-1 accompanied by drawings in Appendix 1.3-2. Table 1.3 3 gives the rod box characteristics.
2.4. Mechanical properties of the fuel rod claddings The cladding material is a Zirconium alloy which conforms to one of the following three criteria:
1 2 Rp0,2 % (MPa) 520 250 and Rm (MPa) 710 400 and At (% sur 50 mm) 12 25 The mechanical behaviour of the zirconium alloys meeting the above criteria, at -40°C, is analysed in the document in Appendix 1.3-3.
The cladding may be possibly pre-oxidised (addition of a thin oxide layer to the cladding tube);
this pre-oxidation of the cladding has no impact on the activity and thermal power calculations presented below.
The claddings may be possibly coated with a chrome thickness up to 30 µm.
The thermal properties of the cladding are detailed in Appendix 2.2-1.
2.5. Zircolay-41 and M5FRAMATOME alloy creep law The laws used to analyse creep-related risks to Zircolay-4 and M5FRAMATOME alloys are presented in Paragraph 2.4 of Chapter 2.2-3 of this report.
2.6. Other particularities The presence of cloth desiccant bags is permitted outside of the cavity.
- 3. Thermal power The thermal power released by the fresh fuel is calculated using the ORIGEN code for the following isotope composition (% by weight) of ERU:
U232: %,
U234: %,
U235: %,
1 The Zr-4 and Zy-4 abbreviations used in the safety analysis report to designate the cladding material appoint the same material, that is to say Zircaloy-4 which is an alloy with zirconium.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 6 of 33 U236: %,
U238: balance for ERU.
The thermal power released per tonne of Uranium is therefore less than W. The isotope composition taken into account is different from that described in § 2.1 but the differences in composition are not such as to call into question the result obtained. A thermal power of W is therefore assumed for the loading of a FCC4 packaging.
- 4. Activity The weights used for the activity calculations are given in the summary tables. For type 17x17 assemblies it is possible to transport rods inserted into the guide-tubes, thereby covering all loading cases.
The activity calculations are therefore carried out for the following configurations:
ENU or ERU fuel Assemblies with fuel rods in the guide-tubes (17x17 only),
Assemblies without fuel rods in the guide-tubes (standard configuration for all assemblies),
Non-assembled fuel rods shipped in rod boxes (also called rod channels).
For ENU and ERU, type 17x17 assemblies and all types of non-assembled rods are analysed with a U235 enrichment of 5 %, and type 16x16 and 18x18 assemblies are analysed with a U235 enrichment of 4.5 % in accordance with Tables 1.3-1 and 1.3-2.
4.1. Activity due to fission products (ERU) 4.2. Activity for ENU According to table 2 of reference [1], the A2 value for ENU with an enrichment up to 20% is unlimited.
Thus, the radioactive materials can be classified as LSA-II according to article 409 of the regulation [1]. Moreover, they contain fissile matters.
The matter is therefore classified as fissile and of Low Specific Activity: LSA-II according to the regulation [1].
Moreover, the number of A2 contained in the radioactive materials is zero, which allows to transport them in a type A package, according to article 429 of [1].
4.3. Activity calculation for ERU In the case of transportation of enriched reprocessed uranium (ERU), the isotope composition given in the table calls for the consideration of a mixture. The A2 value of the mixture is Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 7 of 33 calculated in accordance with Article 405 of reference [1] including fission products (5000 Bq/gU - see paragraph 4.1):
1 232 234 235 236 238 232 234 235 236 238 The activity of the package is determined based on the isotope compositions of ERU as described in § 2.1, the specific activity of the various isotopes determined per reference [1],
and the characteristics of the rods (assemblies or rod channels).
The isotope composition, the specific activity of ERU and the A2 values (including the A2 value of the mixture) are given in Table 1.3-7.
Activity calculations for ERU are given in Table 1.3-8 for assemblies with and without fuel rods in the guide tubes and in Table 1.3-9 for the rod channels.
The total maximum activity per packaging of radioactive materials included in the various ERU contents of the FCC4 is 1.035 TBq, that is 277 A2.
The maximum specific activity of the material for ERU is 2.27x10-4 A2/g.
The mean specific activity of the material is therefore less than 2x10-3 A2/g - criterion for type III material of low specific activity (Article 409 of reference [1]).
Depending on the isotopic composition, the LSA-II classification is also permitted subject to compliance with the A2/g criterion for specific activity.
Therefore:
The material (uranium oxide) is in solid form and uniformly distributed in the solid.
The material is fissile.
The material is classified as Fissile and of Low Specific Activity:
LSA-III according to the Regulation reference [1].
4.4. Compliance with leaching criterion The article 703 of the Regulation reference [1] specifies that the maximum value of activity lost through leaching for an LSA III category material must be less than 0.1 A2, or 3.75x10-4 TBq (see Table 1.3 7). A leaching test for agitated water, presented in Appendix 1.3 4, was carried out on a ERU pellet, and led to the assumption that the activity lost by leaching is less than Bq for an UO2 mass of 10.86 g. The isotopic vector of this pellet is not precisely defined, and it is subsequently assumed, in order to increase the dissolved pellet mass, that the latter is made up of ENU.
According to Table 1.3-4, a pellet of ENU weighing 10.86 g has an activity of 10.86x1.45x105 Bq = 1,57.106 Bq. Thus it is assumed, as a worst-case estimate, that the fraction of activity released during the leaching test (irrespective of the isotopic vector) is
/1.57x106 = .
This fraction of activity released is therefore applied to the maximum calculated activity given in Tables 1.3-8 and 1.3-9, that is 1.035 TBq, which gives 1.035x = TBq, which is well below the criterion of 0.1 A2 = 3.75x10-4 TBq.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 8 of 33 4.5. Compliance with dose rate at 3 metres For the sake of conservatism, the case of enriched reprocessed uranium (ERU) is addressed in this section. Article 517 of reference [1] specifies that the radiation intensity at 3 metres from the unprotected material must not exceed 10 mSv/h.
The dose rate at 3 metres from the material is estimated based on the definition of the A1 value.
As a maximum, the A1 value corresponds to the point activity from a source, producing a DER of 0.1 Sv/h at 1 m. Thus, assuming the contents of the FCC4 packaging to be a point source, an activity of 0.9 A1 will therefore result in a maximum dose equivalent rate at 3 metres of 0.9x1/9x0.1 = 10 mSv/h.
The calculation of A1 for ERU defined in paragraph 2.1 is given in Table 1.3-7. The A1 value of the mixture is calculated in accordance with Article 405 of reference [1] plus the fission products (5000 Bq/gU - see paragraph 4.1):
1 232 234 235 236 238 232 234 235 236 238 The A1 value of the mixture is therefore 17.5 TBq. According to Table 1.3-7 the activity per 1 g of ERU is 8.51x10-7 TBq. An activity of 0.9 A1 therefore corresponds to 18,464 kg of uranium.
The contents described in this chapter can give rise to a maximum uranium mass of 1,216 kg.
Compliance with dose rate criterion at 3 metres is therefore assured.
4.6. Effect of decay of ERU The activity of an ERU assembly is calculated for a period of 5 years after manufacturing in order to evaluate the variation in maximum activity of the contents.
Any impurities and daughter products do not participate in the chemical conversion reaction of UF6 to UO2; as a result, in the production cycle for new ERU-based assemblies the instant T0 corresponds to the conversion and does not therefore take account of daughter products and impurities. Moreover, given that the manufacture of ERU-based assemblies takes place during specific production runs, the production and shipping lead time for these assemblies, once the conversion is complete, is very short, i.e. less than 6 months. The period of 5 years is therefore considered highly conservative.
The decay calculation is carried out using the ORIGEN code for 608 kg of ERU at 5%
enrichment corresponding to a 17x17 XL assembly. Only those isotopes with an activity greater than 1x106 Bq were retained, the others having negligible impact on the total activity of the contents. Fission products were also taken into account in the activity calculation.
The isotopic vector taken into account is as described in § 2.1. The results of this calculation are presented in Table 1.3-10.
At the end of 5 years it is found that the ERU has an activity of A2/gUO2 which here corresponds to A2 for 608 kg of ERU at 5% enrichment.
The activity limit for the LSA-III classification of content is 2x10-3 A2/gU. Thus, inclusion of the daughter products of uranium arising from reprocessing has no impact on the classification of the contents of the FCC4 package models.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 9 of 33
- 5. Definition of maximum radioactive contents The maximum radioactive content (see paragraph 617 of [1]) is defined by fuel assemblies, enriched to a maximum of 5% U235 and a maximum U232 content of 50 ppb (or 0.5x10-6%, the principal parameter influencing the dose equivalent rate).
The package model, with this maximum radioactive content, provides sufficient protection to guarantee, during routine transport conditions, that the intensity of the radiation at any point on the external surface of the package remains below the regulatory criterion for non-exclusive transportation of 2 mSv/h. (In fact, Chapter 2.4 highlights significant margins with respect to this criterion, for a U235 enrichment of 4.95% and a max. U232 content of 50 ppb.
- 6. Conclusion This chapter describes the contents transported in the FCC4 packaging. In particular, the characteristics of the radioactive materials, fuel assemblies and non-assembled rods are presented.
The maximum thermal power for the content is W.
The transported fissile material arising from natural uranium is classed as a fissile material of low specific activity (LSA-II).
The transported fissile material arising from reprocessed uranium is classed as a fissile material of low specific activity (LSA-III).
- 7. References
[1] Regulations for the Safe Transport of Radioactive Materials - at the revision indicated in Chapter 1.2.
[2] Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material -
Safety Guide - at the revision indicated in Chapter 1.2
[3] CRT C996-10: Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 %
235U
[4] ORIGEN ARP: ORNL/TM - 2005/39, Version 6, vol. I, sect. D1.
Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 10 of 33 List of figures Figure Title No. of pages 1.3-1 Fuel assembly type 17x17 - 1300 MWe 1 1.3-2 Fuel assembly type 17x17 - 1450 MWe 1 1.3-3 Fuel assembly type 16x16 1 1.3-4 Fuel assembly type 18x18 1 1.3-5 Fuel assembly type 17x17 EPR 1 1.3-6 Example of RCCA for fuel assemblies type 17x17 EPR 1 1.3-7 Fuel rod channel 1 1.3-8 Drawing of the smooth-walled dummy assembly fitted with spacers 1 1.3-9 Type of fuel assembly - 17x17 GAIA 1 TOTAL 9 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 11 of 33 List of tables Table Title No. of pages 1.3-1 Characteristics of fuel assemblies and rods transported in FCC4 packagings 3 1.3-2 Characteristics of non-assembled fuel rods transported in FCC4 packagings 1 1.3-3 Fuel rod channels 1 1.3-4 Activity of enriched natural uranium fuel (ENU) 1 1.3-5 Maximum activity of ENU assemblies 1 1.3-6 Maximum activity in ENU channels 1 1.3-7 Activity of reprocessed uranium fuel (ERU) 1 1.3-8 Maximum activity of ERU assemblies 1 1.3-9 Maximum activity in ERU channels 1 1.3-10 Decay of enriched reprocessed uranium (ERU) for a 17x17 XL assembly 1 TOTAL 12 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 12 of 33 List of appendices Appendix Title No. of pages 1.3-1 Appendix 1.3-1 DOS-13-00081778-031 "Description of rod boxes for FCC4 containers" 8 1.3-2 Appendix 1.3-2 DOS-13-00081778-032 "Drawings showing rod boxes for FCC4 containers" 2 Framatome document FFDC 05098 revision 3 1.3-3 "Toughness of Zr alloys. Proposal for the specification of cladding materials in transportation 2+8 approval" Test report SQ/95/602Pbo/CC 1.3-4 2+4 "Leaching tests on enriched reprocessed uranium pellets (ERU)"
TOTAL 26 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 13 of 33 Figure 1.3-1 FUEL ASSEMBLY TYPE 17X17 - 1300 MWE Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 14 of 33 Figure 1.3-2 FUEL ASSEMBLY TYPE 17X17 - 1450 MWE Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 15 of 33 Figure 1.3-3 FUEL ASSEMBLY TYPE 16X16 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 16 of 33 Figure 1.3-4 FUEL ASSEMBLY TYPE 18X18 Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 17 of 33 Figure 1.3-5 Fuel assembly type 17x17 EPR Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 18 of 33 Figure 1.3-6 Example of RCCA for fuel assembly type 17x17 EPR Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 19 of 33 Figure 1.3-7 Fuel rod channel Row compensation upper wedge Row compensation intermediate wedge Radial wedge 134 maxi Dimensions in mm Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 20 of 33 Figure 1.3-8 Drawing of the smooth-walled dummy assembly, fitted with spacers Non-proprietary version
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 21 of 33 Figure 1.3-9 Type of fuel assembly - 17x17 GAIA Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 22 of 33 TABLE 1.3-1(1/3)
Characteristics of fuel assemblies and rods transported in FCC4 packagings 17x17 14 foot 17x17 EPR Assembly 16x16 (****) 18x18 (****)
(*) (****) (****)
Top nozzle section (mm)
Bottom nozzle section (mm)
Nominal length (mm)
Mass - maximum tolerances 877 807 867 788 (kg)
Mass - nominal tolerances (kg)
Max. mass of RCCA (kg) 58 60 Grids Minimum number Envelope (mm)
Guide-tubes Number 20 24 24 24 Material Zirconium alloy Zirconium alloy Zirconium alloy Zirconium alloy Nominal outside diameter (mm)
Nominal inside diameter (mm)
Instrumentation tube No No No Material instrumentation Zirconium alloy instrumentation instrumentation tube tube tube Nominal outside diameter 12.45 (mm)
Nominal inside diameter 11.45 (mm)
Fuel rods Number per assembly 264 265 (including any rods placed in 236 300
+ 24 + 24 the guide-tubes)
Pitch (mm) 14.3 12.6 12.7 12.6 Cladding material Zirconium alloy Zirconium alloy Zirconium alloy Zirconium alloy Min. outside diameter (mm) 10.70 9.40 9.46 9.40 Min. thickness (mm) 0.68 0.52 0.60 0.52 Spacers Nominal height (mm) 304.8 304.8 Fissile material (**)
Type of fuel ENU or ERU ENU or ERU ENU or ERU ENU or ERU Maximum pellet diameter 9.14 8.30 8.08 8.30 (mm)
Active nominal rod length 3900 4267 3900 4200 (mm)
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 23 of 33 TABLE 1.3-1(2/3)
Characteristics of fuel assemblies and rods transported in FCC4 packagings 17x17 14 17x17 EPR Assembly 16x16 (****) 18x18 (****)
foot (*) (****) (****)
Maximum mass of heavy metal per assembly (kg) (including any rods 563 608 555 600 placed in the guide-tubes)
Maximum mass of UO2 per assembly (kg) (including any rods placed in the 639 690 630 681 guide-tubes)
Maximum U235 enrichment rate (%) 4.5 5 4.5 5 Maximum pellet density (100 % of 10.96 10.96 10.96 10.96 the theoretical density of UO2)
Fissile cross-section (mm)
Note: Here the term zirconium alloy is understood to mean any non-irradiated zirconium alloy used as a constituent in a PWR or EPR fuel assembly. When used for fuel rod cladding this alloy must also meet the conditions specified in § 2.4.
(*) The 17x17 XLR assembly has the same geometrical characteristics as the 17x17 XL, except for the presence of guide pins on the top nozzle and the longitudinal positioning of the grids.
(**) The pellet height is not a safety feature. In all the criticality studies, it is the height of the fissile column that is modelled.
(***) Nominal length with maximum sleeve height (end of hold-down spring)
(****) Residue of glycerine (a maximum of 5 grams) may be present on each of the assemblies.
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 24 of 33 TABLE 1.3-1(3/3)
CHARACTERISTICS OF FUEL ASSEMBLIES AND RODS TRANSPORTED IN FCC4 PACKAGINGS Assembly 17x17 GAIA (****)
Top nozzle section (mm)
Bottom nozzle section (mm)
Nominal length (mm)
Mass - maximum tolerances (kg) 798 Mass - nominal tolerances (kg)
Max. mass of RCCA (kg) 58 Grids Minimum number Envelope (mm)
Guide-tubes Number 24 Material Zirconium alloy Nominal outside diameter (mm)
Diameter of the upper end (mm)
Instrumentation tube Material Zirconium alloy Nominal outside diameter (mm)
Nominal inside diameter (mm)
Fuel rods Number per assembly (including any rods 264 placed in the guide-tubes) + 24 Pitch (mm) 12.6 Cladding material Zirconium alloy Min. outside diameter (mm) 9.40 Min. thickness (mm) 0.52 Fissile material (**)
Type of fuel ENU Maximum pellet diameter (mm) 8.30 Active nominal rod length (mm) 4267 Maximum mass of heavy metal per assembly (kg) (including any rods placed in the guide- 608 tubes)
Maximum mass of UO2 per assembly (kg) 690 (including any rods placed in the guide-tubes)
Maximum U235 enrichment rate (%) 5 Maximum pellet density (100 % of the 10.96 theoretical density of UO2)
Fissile cross-section (mm)
Note: Here the term zirconium alloy is understood to mean any non-irradiated zirconium alloy used as a constituent of a GAIA fuel assembly. When used for fuel rod cladding this alloy must also meet the conditions specified in § 2.4.
(**) The pellet height is not a safety feature. In all the criticality studies, it is the height of the fissile column that is modelled.
(****) Residue of glycerine (a maximum of 5 grams) may be present on each of the assemblies.
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 25 of 33 TABLE 1.3-2 CHARACTERISTICS OF NON-ASSEMBLED FUEL RODS TRANSPORTED IN FCC4 PACKAGINGS 14x14. 17x17.
Type of rods "8 and 10- 15x15. 16x16. "12 and 14- 18x18. 17x17 EPR foot" foot (*)
Zirconium Zirconium Zirconium Zirconium Material Zirconium alloy Zirconium alloy alloy alloy alloy alloy Cladding Minimum external 10.68 10.68 10.70 9.40 9.46 9.40 diameter (mm)
Minimum thickness 0.57 0.57 0.68 0.52 0.60 0.52 (mm) 2413 (8-foot)
Nominal active length 3658 (12-foot) 3048 (10- 3658 3900 3900 4200 (mm) 4267 (14-foot) foot)
Maximum uranium 235 enrichment per rod 5 5 5 5 5 5
(%)
Maximum pellet 9.4 9.4 9.14 8.3 8.08 8.3 diameter (mm)
(8-(12-foot)
Total nominal length of foot)
(XL, rod (mm) (10-XLR and GAIA) foot)
(8-foot) (12-foot)
Rod mass at maximum (10- (XL, XLR tolerances (kg) foot) and GAIA)
(8-foot) (12-foot)
Rod mass at nominal (10- (XL, XLR tolerances (kg) foot) and GAIA)
Note: Here the term zirconium alloy is understood to mean any non-irradiated zirconium alloy used as a constituent of a PWR fuel assembly. When used for fuel rod cladding this alloy must also meet the conditions specified in § 2.4.
(*) The 17x17 14-foot column corresponds to 17x17 XL, XLR and GAIA fuel assemblies Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 26 of 33 Table 1.3-3 Fuel rod channels 14x14. 17x17.
Type of rods "8 and 10- 15x15. 16x16. "12 and 14- 18x18. 17x17 EPR foot" foot (*)
Max. number of rods per 222/167 148 148 185 205 185 channel Maximum mass of heavy metal 347/330 343 353 335/391 379 384 per channel (kg)
Maximum UO2 mass per 394/374 389 401 380/443 430 436 channel (kg)
Rod mass at max tolerances 471/443 470 504 461/537 544 537 (kg)
Rod mass at nominal tolerances (kg)
Maximum total mass (kg) 856 856 856 856 856 856
(*) The 17x17 14-foot note covers 17x17 XL, XLR and GAIA fuel assemblies Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 27 of 33 Table 1.3-4 Activity of enriched natural uranium fuel (ENU)
Quantity Specific Activity per 1 g Activity per 1 g A2 (TBq)
Isotope (g/g of activity [2] of uranium of uranium IAEA [1]
uranium) (Bq/g) (Bq) (TBq)
U232. 5.00x10-10 7,935.10+11 3.97x10+02 3.97x10-10 -
U234. 5.50x10-04 2,317.10+08 1.27x10+05 1.27x10-07 -
U235. 5.00x10-02 8,014.10+04 4.01x10+03 4.01x10-09 -
U236. 5.00x10-04 2,399.10+06 1.20x10+03 1.20x10-09 -
U238. 9.49x10-01 1,246.10+04 1.18x10+04 1.18x10-08 -
Total (g) 1 1.45x10+05 1.45x10-07 unlimited Quantity Specific Activity per 1 g Activity per 1 g A2 (TBq)
Isotope (g/g of activity [2] of uranium of uranium IAEA [1]
uranium) (Bq/g) (Bq) (TBq)
U232. 5.00x10-10 7,935.10+11 3.97x10+02 3.97x10-10 -
U234. 5.50x10-04 2,317.10+08 1.27x10+05 1.27x10-07 -
U235. 4.50x10-02 8,014.10+04 3.61x10+03 3.61x10-09 -
U236. 5.00x10-04 2,399.10+06 1.20x10+03 1.20x10-09 -
U238. 9.54x10-01 1,246.10+04 1.19x10+04 1.19x10-08 -
Total (g) 1 1.45x10+05 1.45x10-07 unlimited Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 28 of 33 TABLE 1.3-5 Maximum activity of ENU assemblies 17x17 XL + 24 17x17 EPR +
rods in the 24 rods in the 17x17 XL 17x17 EPR guide tubes guide tubes Enrichment (% U235) 5.00 % 5.00 % 5.00 % 5.00 %
Maximum number of rods 288 289 264 265 Max mass of U (kg) 608 600 557 550 Max mass of UO2 (kg) 690 681 632 624 Max activity per assembly 8.8x10-02 8.7x10-02 8.07x10-02 7.97x10-02 (TBq)
Max activity per packaging 0.176 0.174 0.161 0.159 (TBq)
Total activity of a packaging expressed in 0 0 0 0 A2 Average specific activity of the material (UO2 mass) 0 0 0 0 (A2/g)
Criterion of average specific activity for an LSA-II 1.00x10-4 1.00x10-4 1.00x10-4 1.00x10-4 material (A2/g)
Material classification LSA-II LSA-II LSA-II LSA-II 16x16. 18x18.
Enrichment (% U235) 4.50 % 4.50 %
Maximum number of rods 236 300 Max mass of U (kg) 563 555 Max mass of UO2 (kg) 639 630 Max activity per assembly 8.1x10-02 8x10-02 (TBq)
Max activity per 0.163 0.160 packaging (TBq)
Total activity of a packaging expressed in 0 0 A2 Average specific activity of the material (UO2 mass) 0 0 (A2/g)
Criterion of average specific activity for an LSA-II 1.00x10-4 1.00x10-4 material (A2/g)
Material classification LSA-II LSA-II NOTE: The 17x17 XL note covers 17x17 XL, XLR and GAIA fuel assemblies Their activity being 0 A2 < 1 A2, these assemblies can all be transported in type A packages.
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 29 of 33 TABLE 1.3-6 Maximum activity in ENU channels 185 rods 17x17 222 rods 14x14 167 rods 14x14 148 rods 15x15 12-foot 8-foot 10-foot Enrichment (% U235) 5.00 % 5.00 % 5.00 % 5.00 %
Number of rods per channel 185 148 222 167 Max mass of U (kg) 335 343 347 330 Max mass of UO2 (kg) 380 389 394 374 Max activity per 0.097 0.099 0.101 0.096 packaging (TBq)
Total activity of a packaging expressed in 0 0 0 0 A2 Average specific activity of the material (UO2 mass) 0 0 0 0 (A2/g)
Criterion of average specific activity for an LSA-II 1.00x10-4 1.00x10-4 1.00x10-4 1.00x10-4 material (A2/g)
Material classification LSA-II LSA-II LSA-II LSA-II 185 rods 17x17 185 rods 17x17 148 rods 16x16 205 rods 18x18 XL 17x17 XL EPR Enrichment (% U235) 5.00 % 5.00 % 5.0 % 5.0 %
Number of rods per channel 185 185 148 205 Max mass of U (kg) 391 384 353 379 Max mass of UO2 (kg) 443 436 401 430 Max activity per 0.113 0.111 0.102 0.110 packaging (TBq)
Total activity of a packaging expressed in 0 0 0 0 A2 Average specific activity of the material (UO2 mass) 0 0 0 0 (A2/g)
Criterion of average specific activity for an LSA-II 1.00x10-4 1.00x10-4 1.00x10-4 1.00x10-4 material (A2/g)
Material classification LSA-II LSA-II LSA-II LSA-II NOTE: The 17x17 XL rods cover 17x17 XL, XLR and GAIA fuel assemblies Their activity being 0 A2 < 1 A2, these rods loadings can all be transported in type A packages.
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 30 of 33 Table 1.3-7 Activity of enriched reprocessed uranium fuel (ERU)
Quantity Activity per 1 g Specific activity Activity per 1 g A2 (TBq)**
Isotope (g/g of of uranium
[2] (Bq/g) of uranium (Bq) IAEA [1]
uranium) (TBq)
U232. 5.00x10-08 7.9350x10+11 3.9675x10+04 3.9675x10-08 1.00x10-03 U234. 3.00x10-03 2.3170x10+08 6.9510x10+05 6.9510x10-07 6.00x10-03 U235. 5.00x10-02 8.0140x10+04 4.0070x10+03 4.0070x10-09 unlimited U236. 4.00x10-02 2.3990x10+06 9.5960x10+04 9.5960x10-08 6.00x10-03 U238. 9.07x10-01 1.2460x10+04 1.1301x10+04 1.1301x10-08 unlimited FP* - - 5000 5.00x10-09 9.00x10-05 Total (g) 1 8.51x10+05 8.51x10-07 3.75x10-03
- According to table 3 of reference [1], the A2 of fission products is equal to 9x10-5 (, emitters).
- Table 2 of reference [1] for isotopes of U.
Quantity Activity per 1 g Specific activity Activity per 1 g A2 (TBq)**
Isotope (g/g of of uranium
[2] (Bq/g) of uranium (Bq) IAEA [1]
uranium) (TBq)
U232. 5.00x10-08 7.9350x10+11 3.9675x10+04 3.9675x10-08 1.00x10-03 U234. 3.00x10-03 2.3170x10+08 6.9510x10+05 6.9510x10-07 6.00x10-03 U235. 4.50x10-02 8.0140x10+04 3.6063x10+03 3.6063x10-09 unlimited U236. 4.00x10-02 2.3990x10+06 9.5960x10+04 9.5960x10-08 6.00x10-03 U238. 9.07x10-01 1.2460x10+04 1.1301x10+04 1.1301x10-08 unlimited FP* - - 5000 5.00x10-09 9.00x10-05 Total (g) 1 8.46x10+05 8.46x10-07 3.75x10-03
- According to table 3 of reference [1], the A2 of fission products is equal to 9x10-5 (, emitters).
- Table 2 of reference [1] for isotopes of U.
Quantity Activity per 1 g Specific activity Activity per 1 g A1 (TBq)**
Isotope (g/g of of uranium
[2] (Bq/g) of uranium (Bq) IAEA [1]
uranium) (TBq)
U232. 5.00x10-08 7.9350x10+11 3.9675x10+04 3.9675x10-08 10 U234. 3.00x10-03 2.3170x10+08 6.9510x10+05 6.9510x10-07 40 U235. 5.00x10-02 8.0140x10+04 4.0070x10+03 4.0070x10-09 unlimited U236. 4.00x10-02 2.3990x10+06 9.5960x10+04 9.5960x10-08 40 U238. 9.07x10-01 1.2460x10+04 1.1301x10+04 1.1301x10-08 unlimited FP* - - 5000 5.00x10-09 0.2 Total (g) 1 8.51x10+05 8.51x10-07 17.5
- According to table 3 of reference [1], the A1 of fission products is equal to 0.2 (, emitters).
- Table 2 of reference [1] for isotopes of U.
Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 31 of 33 TABLE 1.3-8 Maximum activity of ERU assemblies 17x17 XL + 24 17x17 EPR + 24 rods in the guide rods in the guide 17x17 XL 17x17 EPR tubes tubes Enrichment (% U235) 5.00 % 5.00 % 5.00 % 5.00 %
Maximum number of rods 288 289 264 265 Max mass of U (kg) 608 600 557 550 Max mass of UO2 (kg) 690 681 632 624 Max activity per assembly 0.517 0.511 0.474 0.468 (TBq)
Max activity per packaging 1.035 1.021 0.948 0.936 (TBq)
Total activity of a packaging 277 A2 273 A2 253 A2 250 A2 expressed in A2 Average specific activity of the material (UO2 mass) 2.00x10-04 2.00x10-04 2.00x10-04 2.00x10-04 (A2/g)
Criterion of average specific activity for an LSA-III material 2.00x10-03 2.00x10-03 2.00x10-03 2.00x10-03 (A2/g)
Material classification LSA-III LSA-III LSA-III LSA-III 16x16. 18x18.
Enrichment (% U235) 4.50 % 4.50 %
Maximum number of rods 236 300 Max mass of U (kg) 563 555 Max mass of UO2 (kg) 639 630 Max activity per assembly 0.479 0.472 (TBq)
Max activity per packaging 0.958 0.944 (TBq)
Total activity of a packaging expressed in 256 A2 252 A2 A2 Average specific activity of the material (UO2 mass) 2.00x10-04 2.00x10-04 (A2/g)
Criterion of average specific activity for an LSA-III 2.00x10-03 2.00x10-03 material (A2/g)
Material classification LSA-III LSA-III NOTE: The 17x17 XL note covers 17x17 XL and XLR fuel assemblies Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 32 of 33 TABLE 1.3-9 MAXIMUM ACTIVITY OF ERU CHANNELS 185 rods 17x17 222 rods 14x14 8- 167 rods 14x14 148 rods 15x15 12-foot foot 10-foot Enrichment (% U235) 5.00 % 5.00 % 5.00 % 5.00 %
Number of rods per channel 185 148 222 167 Max mass of U (kg) 335 343 347 330 Max mass of UO2 (kg) 389 394 374 Max activity per channel (TBq) 0.285 0.292 0.295 0.281 Max activity per packaging 0.570 0.584 0.591 0.562 (TBq)
Total activity of a packaging 152 A2 156 A2 158 A2 150 A2 expressed in A2 Average specific activity of the material (UO2 mass) 2.27x10-04 2.27x10-04 2.27x10-04 2.27x10-04 (A2/g)
Criterion of average specific activity for an LSA-III material 2.00x10-03 2.00x10-03 2.00x10-03 2.00x10-03 (A2/g)
Material classification LSA-III LSA-III LSA-III LSA-III 185 rods 17x17 185 rods 17x17 148 rods 16x16 205 rods 18x18 XL 17x17 XL EPR Enrichment (% U235) 5.00 % 5.00 % 5.00 % 5.00 %
Number of rods per channel 185 185 148 205 Max mass of U (kg) 391 384 353 379 Max mass of UO2 (kg) 443 436 401 430 Max activity per channel (TBq) 0.333 0.327 0.300 0.323 Max activity per packaging 0.666 0.654 0.601 0.645 (TBq)
Total activity of a packaging 178 A2 174 A2 160 A2 172 A2 expressed in A2 Average specific activity of the material (UO2 mass) 2.27x10-04 2.27x10-04 2.27x10-04 2.27x10-04 (A2/g)
Criterion of average specific activity for an LSA-III material 2.00x10-03 2.00x10-03 2.00x10-03 2.00x10-03 (A2/g)
Material classification LSA-III LSA-III LSA-III LSA-III NOTE: The 17x17 XL rods cover 17x17 XL and XLR fuel assemblies Non-proprietary version
Formulaire : PM04-4-MO-6E rev. 02 Unrestricted Orano Orano NPS Identification : DOS-19-021166-002-NPV Vers. 2.0 Page 33 of 33 TABLE 1.3-10 DECAY OF ENRICHED REPROCESSED URANIUM (ERU) FOR A 17X17 XL ASSEMBLY Non-proprietary version