Development of the Enigma Fuel Performance Code for Whole Core Analysis and Dry Storage Assessments

Rossiter, Glyn

doi:10.5516/net.2011.43.6.489

Cited by 46 publications

(17 citation statements)

References 4 publications

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“…The main design philosophy of FINIX is to provide a simple but sufficient model of the fuel rod that can be used in different types of simulation codes, including neutronics, reactor dynamics, thermal hydraulics, and system codes. While multiphysics capabilities can also be achieved with direct code-tocode coupling (see, e.g., Hämäläinen et al, 2001;Rossiter, 2011), such approach is often laborious when highly specialized software is involved. Thus, in the design of the FINIX code, flexibility of the interface between FINIX and the main simulation code has been prioritized.…”

Section: General Descriptionmentioning

confidence: 99%

Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Ikonen

Loukusa

Syrjälahti

et al. 2015

Annals of Nuclear Energy

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Section: General Descriptionmentioning

confidence: 99%

Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Ikonen

Loukusa

Syrjälahti

et al. 2015

Annals of Nuclear Energy

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“…(formerly AMEC Foster Wheeler) and EdF UK is required to provide a licensing grade code system that can be based on upgrading their industrially applied nodal code PANTHER [46] and the lattice code system WIMS [47]. The fuel performance code could be delivered by NNL with their ENIGMA code [14], which is already an industrial-grade application. The transport code is already available at the University of Liverpool [48,49].…”

Section: Code Development Strategymentioning

confidence: 99%

“…However, the two-step scheme, which consists of a lattice calculation to produce a few homogenized cross-section sets for the nodal core simulation, is still standard within industry. In addition, there is the offline procedure for the pin power reconstruction to obtain access to the pin-wise power distribution and the temperatures for the fuel rod modelling that are required for the safety evaluation, even if these processes are, in part, highly automatized today [14]. In contrast to the application scheme, a very comprehensive overview on the scientific challenges for reactor physics has been given in the special edition of the PHYSOR 2012 conference [15].…”

Section: Introductionmentioning

confidence: 99%

On a Roadmap for Future Industrial Nuclear Reactor Core Simulation in the U.K. to Support the Nuclear Renaissance

et al. 2018

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The U.K. has initiated the nuclear renaissance by contracting for the first two new plants and announcing further new build projects. The U.K. government has recently started to support this development with the announcement of a national programme of nuclear innovation. The aim of this programme with respect to modelling and simulation is foreseen to fulfil the demand in education and the build-up of a reasonably qualified workforce, as well as the development and application of a new state-of-the-art software environment for improved economics and safety. This document supports the ambition to define a new approach to the structured development of nuclear reactor core simulation that is based on oversight instead of looking at detail problems and the development of single tools for these specific detail problems. It is based on studying the industrial demand to bridge the gap in technical innovation that can be derived from basic research in order to create a tailored industry solution to set the new standard for reactor core modelling and simulation for the U.K. However, finally, a technical requirements specification has to be developed alongside the strategic approach to give code developers a functional specification that they can use to develop the tools for the future. Key points for a culture change to the application of modern technologies are identified in the use of DevOps in a double-strata approach to academic and industrial code development. The document provides a novel, strategic approach to achieve the most promising final product for industry, and to identify the most important points for improvement.

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“…The forecasting of fuel assembly behavior during dry long-term storage can be implemented based on calculated data obtained by computer codes. However, the main disadvantage of such forecasting is that the data used the nonirradiated and unaged material as initial design parameters [9,10].…”

Section: Introductionmentioning

confidence: 99%

The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA

Koyanbayev

Skakov

Batyrbekov

et al. 2019

Science and Technology of Nuclear Installations

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There are results of long-term thermal aging of samples of irradiated and nonirradiated FA jacket and nonirradiated fuel element cladding at a temperature range from 300 to 550°C in argon, to 600°C in air. Materials have been studied before and after thermal tests. The forecast estimation of expected corrosion damage of barrier material at the radionuclide release from spent fuel assemblies of BN-350 reactor into environment during dry storage for 50 years was carried out.

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Development of the Enigma Fuel Performance Code for Whole Core Analysis and Dry Storage Assessments

Cited by 46 publications

References 4 publications

Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Module for thermomechanical modeling of LWR fuel in multiphysics simulations

On a Roadmap for Future Industrial Nuclear Reactor Core Simulation in the U.K. to Support the Nuclear Renaissance

The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA

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