Výsledky vyhledávání

Akademický článek

VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS

Autor: Smith Peter, Hosking Glynn, Tollit Brendan, Lindley Ben, Cox Andrew, Perry Ray, Ware Tim, Mason Robert, Stefanowska Magda

Publikováno v: EPJ Web of Conferences, Vol 247, p 03020 (2021)

The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liqu

Externí odkaz: https://doaj.org/article/2a662cbe32e44f0cbd918361450daad3

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Akademický článek

FAST REACTOR MULTIPHYSICS AND UNCERTAINTY PROPAGATION WITHIN WIMS

Autor: Lindley Ben, Tollit Brendan, Smith Peter, Charles Alan, Mason Robert, Ware Tim, Perry Ray, Lavarenne Jean, Davies Una, Gregg Robert

Publikováno v: EPJ Web of Conferences, Vol 247, p 06002 (2021)

For liquid metal-cooled fast reactors (LMFRs), improved predictive modelling is desirable to facilitate reactor licensing and operation and move towards a best estimate plus uncertainty (BEPU) approach. A key source of uncertainty in fast reactor cal

Externí odkaz: https://doaj.org/article/a41b159550b04ffdbbb484b55bf958ac

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Akademický článek

Processing and application of nuclear data for low temperature criticality assessment

Autor: Ware Tim, Hanlon David, Hanlon Tara, Hiles Richard, Lingard Malcolm, Perry Ray, Richards Simon

Publikováno v: EPJ Web of Conferences, Vol 239, p 14006 (2020)

Until recently, criticality safety assessment codes had a minimum temperature at which calculations can be performed. Where criticality assessment has been required for lower temperatures, indirect methods, including reasoned argument or extrapolatio

Externí odkaz: https://doaj.org/article/c4a1ddeb996b4b27ae52d3b696a00357

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Akademický článek

Validation of JEFF-3.3 and ENDF/B-VIII.0 nuclear data libraries in ANSWERS codes

Autor: Ware Tim, Hanlon David, Hosking Glynn, Perry Ray, Richards Simon

Publikováno v: EPJ Web of Conferences, Vol 239, p 19001 (2020)

The JEFF-3.3 and ENDF/B-VIII.0 evaluated nuclear data libraries were released in December 2017 and February 2018 respectively. Both evaluations represent a comprehensive update to their predecessor evaluations. The ANSWERS Software Service produces t

Externí odkaz: https://doaj.org/article/a640c65928e74505811834786c63a90b

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Akademický článek

Determining the nuclear data uncertainty on MONK10 and WIMS10 criticality calculations

Autor: Ware Tim, Dobson Geoff, Hanlon David, Hiles Richard, Mason Robert, Perry Ray

Publikováno v: EPJ Web of Conferences, Vol 146, p 06023 (2017)

The ANSWERS Software Service is developing a number of techniques to better understand and quantify uncertainty on calculations of the neutron multiplication factor, k-effective, in nuclear fuel and other systems containing fissile material. The unce

Externí odkaz: https://doaj.org/article/21b4fc7196244961ba3d6a2e0ad0ff67

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