Development of a SKB burn-up credit methodology for BWR
Creators
- 1. Swedish Nuclear Fuel and Waste Management Company (SKB), Solna (Sweden)
- 2. Vattenfall Nuclear Fuel, Solna (Sweden)
Description
Burn-up credit (BUC) is used for PWR in many different applications. However, not many companies have developed and licensed a burn-up credit methodology for BWR. The main difficulty for BWR is the large variation of fuel assembly operational history. In addition to the power history, different BWR-assemblies have different void history and different control rod history. These parameters not only effect the axial BU-profile but also have a great impact on the isotopic composition. Furthermore, BWR-assemblies displays a large variety in fuel designs. All this put together makes it very costly to develop a BU-loading curve which is conservative for all possible conditions and for all different fuel types. SKB Burn-Up credit methodology for PWR was approved by the Swedish Radiation Safety Authority (SSM) in 2017. During 2023 SKB and Vattenfall have further developed this methodology to also cover BWR. The main features are: - Differences in axial BU-profile (End effect) is taken care of by analyzing the core follow calculations. A bounding profile is chosen to ensure conservative treatment. - Control rod history affects are based on control rod presence from real operational history. - Conservative values are also used for void history in a bounding manner. - Uncertainties in calculated isotopic composition and BU is based on conservative assumptions. Scale 6.2 is used for criticality calculations and the validation is using a ck-based methodology. This paper presents how SKB has developed a BWR BUC methodology taking into consideration the above described difficulties and the main results of the uncertainty evaluations. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the 12th international conference on nuclear criticality safety (ICNC2023)
- Imprint Pagination
- 48 p.
- Journal Page Range
- 9 p.
- Report number
- JAEA-Conf--2024-001
Conference
- Title
- 12. international conference on nuclear criticality safety
- Acronym
- ICNC2023
- Dates
- 1-6 Oct 2023
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 56006717
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; CONTROL ELEMENTS; CRITICALITY; FISSION PRODUCTS; FUEL ASSEMBLIES; ISOTOPE RATIO; NUCLEAR FUELS; POWER DENSITY; RADIATION PROTECTION; REACTIVITY; VOID FRACTION
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 5 figs., 2 tabs.; Also available as CD-ROM Data in PDF format, Folder Name: Session04_-Oct3_-T05 in T05_-Oral, Paper ID: of5_-0_-101_-0_-5569791.pdf