Overview of the recent BWR burnup credit project at Oak Ridge National Laboratory
Creators
- Marshall, W.J.1
- Ade, B.J.1
- Gauld, I.C.1
- Ilas, G.1
- Mertyurek, U.1
- Clarity, J.B.1
- Radulescu, G.1
- Betzler, B.R.1
- Bowman, S.M.1
- Martinez-Gonzalez, J.S.2
- Nuclear Energy Agency - NEA, 46 quai Alphonse Le Gallo, 92100 Boulogne-Billancourt (France)
- Institut de Radioprotection et de Surete Nucleaire - IRSN, 31 avenue de la Division Leclerc, 92260 Fontenay-aux-Roses (France)
- 1. Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 (United States)
- 2. Nuclear Energy Agency - NEA, 46, quai Alphone Le Gallo, 92100 Boulogne-Billancourt (France)
Description
Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have completed a five-year program to investigate burnup credit (BUC) for boiling-water reactor (BWR) spent nuclear fuel (SNF) stored in storage and transportation systems. The project examined both peak reactivity BUC, also sometimes called gadolinium credit, and extended BWR BUC. Here extended refers to credit for burnups beyond that associated with peak reactivity. The findings related to peak reactivity BUC are summarized in NUREG/CR7194, and four additional NUREG/CR documents present the results of the studies of extended BWR BUC. The first of these documents, NUREG/CR-7224, presents results of investigations to determine the effects of axial moderator density profiles, control blade use, and axial burnup profiles. Studies on the impact of core operating conditions and assembly-specific depletion conditions are addressed in NUREG/CR-7240, validation of depleted SNF isotopic predictions is addressed in NUREG/CR-7251, and validation of keff calculations for extended BWR BUC are discussed in NUREG/CR-7252. A summary of the entire project, including major conclusions regarding each of the studies, is included in this paper. (authors)
Files
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- INIS-FR--21-0246
Conference
- Title
- ICNC 2019 - 11. international conference on nuclear criticality safety
- Dates
- 15-20 Sep 2019
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52015191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; REACTIVITY; SAFETY MARGINS; SPENT FUEL STORAGE; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; STORAGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 17 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses