DS397 Saf Use Mod RRs with NUSSC comments 18-06-2010

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• normal operation;• special measurements or actions;• emergency situations.4.8. ShieldingDescription of shielding provisions, specifications of anticipated radiation levels in serviceareas during:• normal operation including post irradiation handling;• specific measurements;• emergency situations.5. CHARACTERISTICS 195.1. Nuclear characteristics• Specification of anticipated fluence rate values.• Description of (or reference to) measurements and/or calculations made to verify thefluence rate characteristics:a. prior to irradiation;b. during irradiation (dosimetry).• Reference to or summary of calculated and applied nuclear data.5.2. Reactivity and criticality characteristicsSpecification (based upon calculation and/or measurement) of:a. criticality aspects,b. reactivity effect of entire in-core facility in case it was removed from the core at once,with respect to a waterhole,c. reactivity effect associated with voids which can be filled with water in case of leakage,d. reactivity aspects in case of fast movement of the experimental facility5.3. Radioactivity characteristicsCalculation of total activity of radio nuclides produced in:• irradiation target (if fissionable, specify all noble gases, halogens, actinides and otherdangerous nuclides);• gases, liquids, which may escape due to containment failure;• structural parts of in-pile assembly.All calculations to be relevant for the end of the anticipated irradiation period:• calculation of the decrease in radioactivity due to decay of the major activity contributorsat end of irradiation, 10 hours, 10 days and 100 days after the end of irradiation.19 The main section of the report should mostly contain the results (tables, graphs) of the various calculations.Detailed calculations should either be reported in appendices to the safety report or in separate reports which will bereferred to in the safety analysis report of the utilization project.50
5.4. Thermal characteristics• Calculation of specific heating rates (due to nuclear fission and nuclear heating) of all incorematerials.• Calculation of:a. radial and axial heat flux density and temperature distribution;b. coolant temperature increase.• Calculation of temperature control margin which can be achieved by the available controlsystems (heaters, mixed gas systems).• Calculation of the margin against film boiling (burn-out), under the worst possibleoperating conditions (max. power, minimum cooling), applying all relevant uncertainty(hot spot) factors. A justification of the correlation(s) used must be given.Remark:All calculations are to be made for nominal reactor power, and cooling conditions as well asduring accident and reactor shutdown power.5.5. Mechanical and thermal stress characteristicsThe calculation methods and the applied criteria should be described for all safety relatedmechanical components. The tensile, thermal and admissible stresses should be presented andspecial attention should be addressed to:• transient behaviour;• containment lids;• cryogenic material behaviour;• standard gas supply pressures.6. FABRICATION, ASSEMBLY AND COMMISSIONING6.1. Fabrication6.2. Assembly6.3. CommissioningSummarized description of the quality programme, with amongst others incoming goodsinspection, inspection and testing during assembling and final inspection and testing, to whichthe irradiation facility will be subjected prior to operation. The detailed management systemprogramme must separately be documented, i.e. in a quality assurance/quality control reportand a commissioning report.7. OPERATION AND PERIODICAL TESTING7.1. GeneralOutline of check-out, startup, operation, special measurements and emergency procedures.The detailed operation and handling must be specified in a separate "Operation and HandlingManual".In this section, special periodic testing requirements and dedicated check-out procedures, tobe performed by the project engineer, should be described. In case of extended programmes,reference could be made to a special document.51
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IAEA SAFETY STANDARDSDS 397 Draft 4
Page 7 and 8: 1. INTRODUCTIONBACKGROUND1.1. This
Page 11 and 12: - Resource management includes meas
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Page 45 and 46: REFERENCES[1] EUROPEAN ATOMIC ENERG
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DS397 Saf Use Mod RRs with NUSSC comments 18-06-2010

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