ISO 11311:2011 PDF
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 13
- Дата публикации:
- 5 июля 2011 г.
- Издание:
- ISO IS 11311 edition 1 version 1
- ICS:
- 27.120.30
ISO 11311:2011 specifies common reference critical values (of which the effective neutron multiplication factor, keff, is equal to 1) for homogeneous water-moderated plutonium-uranium oxide mixtures based on an inter-code comparison of calculated critical values. It is applicable to operations with unirradiated mixed uranium-plutonium oxide (MOX) outside nuclear reactors. A classical validation approach for these systems is difficult because of the paucity of critical experiments for MOX fuel. Various reference systems, in terms of isotopic compositions, thicknesses of water reflection, and densities of oxide are evaluated by different combinations of calculation codes and nuclear data libraries (i.e. different calculation schemes). The critical values defined in ISO 11311:2011 are the lowest of those calculated by each of these calculation schemes and accepted as credible. The values in ISO 11311:2011 are reference values and not absolute critical values.
Abstract
Overview
ISO 11311:2011 - Nuclear criticality safety - Critical values for homogeneous plutonium‑uranium oxide fuel mixtures outside of reactors - provides reference critical values for unirradiated mixed uranium‑plutonium oxide (MOX) systems moderated and reflected by water. Based on an inter‑code comparison of multiple calculation schemes and nuclear data libraries, the standard identifies conservative, reference critical values (keff = 1) for a set of credible MOX compositions, densities, geometries and reflector conditions. These values are intended to support criticality safety assessments for operations outside reactors (fabrication, handling, storage, transport).
Key topics and technical requirements
- Fissile media definitions: homogeneous mixtures of UO2 and PuO2 with specified plutonium mass fractions (notably 35.0% and 12.5%) and defined oxide density ranges (up to 3.50 g/cm3 for 35% Pu; up to 11.03 g/cm3 for 12.5% Pu).
- Isotopic cases: three representative plutonium isotopic compositions (P0, P5, P20) are evaluated to bound practical MOX variants.
- Moderation conditions: limited moderation (water mass fraction ≤ 3.0%) and optimum moderation conditions are considered to capture conservative critical behavior for damp powders and mixtures.
- Geometries and reflectors: canonical geometries (sphere, infinite-length cylinder, infinite-section slab) with close‑fitting water reflectors of 2.5 cm and 30.0 cm are used to present critical dimensions and parameters.
- Calculation and validation approach: values are the lowest results from inter‑code comparisons using both deterministic and Monte‑Carlo transport methods and multiple nuclear data libraries (examples include MCNP, SCALE, APOLLO2, TRIPOLI, MONK). For each case at least four different codes and four libraries contributed.
- Use and interpretation requirements:
- Criticality safety assessors must compare their own calculated critical values with those in Annexes C–F.
- In absence of technical justification, the assessor should adopt the lower of the two values; discrepancies must be investigated and justified.
- Subcritical limits and safety margins should be set in accordance with ISO 1709, taking into account experimental paucity and calculation interpretation.
Applications and users
ISO 11311:2011 is practical for:
- Criticality safety engineers and analysts in MOX fuel fabrication and handling facilities
- Process designers and equipment engineers defining geometry and moderation controls
- Regulatory bodies and licensing authorities reviewing safety cases
- QA, training and audit teams developing procedures for storage, transport and processing of unirradiated MOX
Use of the standard helps define conservative process limits (masses, dimensions, densities, moderation) and supports defensible subcritical limits for operational and licensing purposes.
Related standards
- ISO 1709 - Principles for criticality safety in storing, handling and processing (used for subcritical limits and margins)
- ISO 921 - Nuclear energy vocabulary (terms and definitions used)
Keywords: ISO 11311:2011, nuclear criticality safety, MOX fuel, plutonium‑uranium oxide, keff, water‑moderated, inter‑code comparison, critical values, critical dimensions, Monte‑Carlo, deterministic codes.
Технические детали
- Технический комитет
- ISO/TC 85/SC 5 - Nuclear installations, processes and technologies
- SKU
- ISO 11311:2011
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