Effects of fuel temperature history approximations on neutronics properties of a BWR assembly

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.
Original languageEnglish
Title of host publicationProceedings of the PHYSOR 2018, Cancun, Mexico
PublisherAmerican Nuclear Society ANS
Pages2215-2226
Number of pages12
Publication statusAccepted/In press - 2018
MoE publication typeNot Eligible
EventPHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems - Cancun, Mexico
Duration: 22 Apr 201826 Apr 2018

Conference

ConferencePHYSOR 2018
Abbreviated titlePHYSOR 2018
CountryMexico
CityCancun
Period22/04/1826/04/18

Fingerprint

Boiling water reactors
Actinides
Temperature
Gadolinium
Isotopes
Mirrors

Cite this

Valtavirta, V., & Leppänen, J. (Accepted/In press). Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. In Proceedings of the PHYSOR 2018, Cancun, Mexico (pp. 2215-2226). American Nuclear Society ANS.
Valtavirta, Ville ; Leppänen, Jaakko. / Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS, 2018. pp. 2215-2226
@inproceedings{d5c37c1050e74fd899d1a051c324cd52,
title = "Effects of fuel temperature history approximations on neutronics properties of a BWR assembly",
abstract = "We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.",
author = "Ville Valtavirta and Jaakko Lepp{\"a}nen",
year = "2018",
language = "English",
pages = "2215--2226",
booktitle = "Proceedings of the PHYSOR 2018, Cancun, Mexico",
publisher = "American Nuclear Society ANS",
address = "United States",

}

Valtavirta, V & Leppänen, J 2018, Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. in Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS, pp. 2215-2226, PHYSOR 2018, Cancun, Mexico, 22/04/18.

Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. / Valtavirta, Ville; Leppänen, Jaakko.

Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS, 2018. p. 2215-2226.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

T1 - Effects of fuel temperature history approximations on neutronics properties of a BWR assembly

AU - Valtavirta, Ville

AU - Leppänen, Jaakko

PY - 2018

Y1 - 2018

N2 - We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.

AB - We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.

M3 - Conference article in proceedings

SP - 2215

EP - 2226

BT - Proceedings of the PHYSOR 2018, Cancun, Mexico

PB - American Nuclear Society ANS

ER -

Valtavirta V, Leppänen J. Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. In Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS. 2018. p. 2215-2226