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=== set inventory === '''set inventory''' ''ID<sub>1</sub>'' ''ID<sub>2</sub>'' ... Defines the nuclides or elements to include in the [[Description_of_output_files#Burnup_calculation_output|depletion output file]] <tt>[input]_dep.m</tt>. Input values: {| | <tt>''ID<sub>n</sub>''</tt> | : Identifier for nuclide, or element or special entry. |} <u>Notes:</u> *Besides the nuclides or elements specified, the output includes the sum over all isotopes. *Nuclides are entered using element symbol and mass number (e.g U-235, Am-242m, etc.) or ZAI (922350, 952421, etc.). **In the ZAI format the last digit refers to the isomeric state (0 = ground state, 1 = isomeric state). **For more information, see the detailed description on [[Definitions, units and constants#definitions|Nuclide IDs]] *Elements are entered using symbol or numerical (U, 92, etc.). *Special entries include: ::{| class="wikitable" style="text-align: left;" ! Key-word ! Description |- | <tt>all</tt> | all nuclides |- | <tt>accident</tt> | nuclides with significant health impact & high migration probability in accident conditions<ref>''"Chernobyl: Assessment of Radiological and Health Impacts"'', OECD/NEA2002 [https://www.oecd-nea.org/jcms/pl_13598/chernobyl-assessment-of-radiological-and-health-impacts-2002 (2002)]</ref> |- | <tt>actinides</tt> | actinides (Z>88) for which cross section data are found in JEFF-3.1.1 |- | <tt>burnupcredit</tt> | nuclides commonly considered in burnup credit criticality analyses for PWR fuels <ref name="soar">''"Spent Nuclear Fuel Assay Data for Isotopic Validation"'', NEA/NSC/WPNCS/DOC(2011)5 [http://www.oecd-nea.org/science/wpncs/ADSNF/SOAR_final.pdf (2011)]</ref> |- | <tt>burnupindicators</tt> | burnup indicators (commonly measured from spent fuel) <ref name="soar"/> |- | <tt>cosi6</tt> | inventory list used by the COSI6 code (excluding lumped fission products) |- | <tt>lanthanides</tt> | lanthanides (56<Z<72) for which cross section data are found in JEFF-3.1.1 |- | <tt>longterm</tt> | relevant radionuclides in long-term waste analyses <ref>"''The identification of radionuclides relevant to long-term waste management in th United Kingdom''", Nirex Report no. N/105 [https://webarchive.nationalarchives.gov.uk/ukgwa/20211004151355/https://rwm.nda.gov.uk/publication/the-identification-of-radionuclides-relevant-to-long-term-waste-management-in-the-united-kingdom-nirex-report-n105-november-2004/ (2004)]</ref> |- | <tt>minoractinides</tt> | minor actinides (actinides - thorium - uranium - plutonium) for which cross section data are found in JEFF-3.1.1 |- | <tt>fp</tt> | fission products |- | <tt>dp</tt> | actinide decay products (from Serpent 1) |- | <tt>ng</tt> | noble gases |} *The detailed list of nuclides associated with each special entry: [[Pre-defined inventory lists|Pre-defined inventory lists]] '''set inventory''' '''top''' ''N'' ''PARA'' Defines the criterion or variable based on which to include the most significant contributors under that category in the depletion output file <tt>[input]_dep.m</tt>. Input values: {| | <tt>''N''</tt> | : Number of nuclides |- | <tt>''PARAM''</tt> | : Parameter name |} <u>Notes:</u> *The contribution criterion is based on the variables evaluated in the depletion calculation and outputted in the bunurp output. *The possible key-words/variables are: ::{| class="wikitable" style="text-align: left;" ! Key-word ! Description |- | <tt>mass</tt> | contribution to mass fraction |- | <tt>activity</tt> | contribution to activity |- | <tt>dh</tt> | contribution to decay heat |- | <tt>sf</tt> | contribution to spontaneous fission rate |- | <tt>gsrc</tt> | contribution to gamma emission rate |- | <tt>ingtox</tt> | contribution to ingestion toxicity |- | <tt>inhtox</tt> | contribution to inhalation toxicity |} *For example: "top 10 dh" gives the top 10 contributors to decay heat. *The special entries and the calculation of top contributors do not work with the re-depletion [[Installing and running Serpent#Running Serpent|<tt>''-rdep''</tt>]] command line option.
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