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Research Articles

Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code

ORCID Icon, , , &
Pages 324-353 | Received 19 Dec 2022, Accepted 20 Jun 2023, Published online: 21 Aug 2023
 

Abstract

This paper presents the fuel performance simulation of two past experiments that are concerned with partial fuel melting. The activity is conducted in the framework of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Power to Melt and Maneuverability (P2M) – Second Framework for Irradiation Experiments (FIDES-II) Joint ExpErimental Programme (JEEP). The xM3 transient experiment involved uranium oxide (UO2) fuel with a ZIRconium Low Oxidation alloy (ZIRLO) cladding base irradiated up to 27 MWd/kg U, followed a ramp test up to 70 kW/m leading to inception of melting. The High Burnup Chemistry Experiment 4 (HBC4) transient was performed according to a rapid power ramp, on a UO2 fuel with a Zircaloy-4 cladding base irradiated up to 47 MWd/kg U. The linear heat generation rate reached 66.3 kW/m at the end of the transient leading to inception of melting and rodlet failure. Three main cases per each of the two transients were modeled with the TRANSURANUS code version 2015 in agreement with the benchmark specifications to consider uncertainty on the power during the ramping phases. The paper presents and discusses the analysis of these tests and provides an in-depth sensitivity analysis to assess the capabilities of the code as well as the effect of user choices in simulating the base irradiation and the inception of melting in light water reactor fuel rods.

Acronyms

AR:=

after ramp

BI:=

base irradiation

BR2:=

Belgian Reactor 2

BR3:=

Belgian Reactor 3

CRP:=

Coordinated Research Project

EPRI:=

Electric Power Research Institute

EPRI/C-E/KWU:=

Electric Power Research Institute/Combustion Engineering/Kraftwerk Union

FGR:=

fission gas release

FIDES-II:=

Second Framework for Irradiation Experiments

FP:=

fission product

HBC4:=

High Burnup Chemistry Experiment 4

HBS:=

high-burnup structure

IAEA:=

International Atomic Energy Agency

ITU:=

Institute for Transuranium Elements (Karlsruhe)

JEEP:=

Joint ExpErimental Programme

LHGR:=

linear heat generation rate (also referred as LHR)

LHR:=

linear heating rate

LWR:=

light water reactor

OECD/NEA:=

Organisation for Economic Co-operation and Development/Nuclear Energy Agency

P2M:=

Power to Melt and Maneuverability

PCI:=

pellet-to-cladding interaction

PCMI:=

pellet-to-cladding mechanical interaction

PIE:=

postirradiation examinations

PWC:=

pressurized water capsule

PWC-CD:=

pressurized water capsule and calorimetric device

PWR:=

pressurized water reactor

R2:=

Studsvik Research Reactor 2

RTL:=

ramp terminal level

SCC:=

iodine induced stress corrosion cracking

TU:=

TRANSURANUS code

UO2:=

uranium oxide

ZIRLO:=

ZIRconium Low Oxidation alloy

Zry:=

Zircaloy

Zr2:=

Zircaloy-2

Zr4:=

Zircaloy-4

1-D:=

one-dimensional

3-D:=

three-dimensional

Nomenclature

bu ==

burnup (MWd/kg U)

Cpu ==

plutonium concentration percent in weight (% wt)

cpu ==

plutonium concentration weight fractional (/wt)

cw ==

normalized amount of cold working

E/E’ ==

Young’s modulus (MPa)

Tmelt-sol ==

solidus melting temperature (℃)

Tmelt-liq ==

liquidus melting temperature (℃)

u ==

displacement induced by relocation (mm)

υ/υ’ ==

Poisson number

Greek

εi ==

strain into the direction i

Ө ==

cladding average temperature (℃)

Φt ==

fast neutrons (E > 0.82 MeV) fluence (neutron/cm2)

Acknowledgments

We wish to thank the members of the fuel modeling group of ITU for their generous availability and technical support. P2M is an activity conducted and funded through the Nuclear Energy Agency Joint International Project, Framework for Irradiation Experiments (FIDES). V. D’Ambrosi is kindly acknowledged for fruitful discussions during the preparation of this paper.

Disclosure Statement

No potential conflict of interest was reported by the author(s).

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