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Division of
Applied nuclear
physics
Scientific Head
Professor Ane Håkansson
Admin. Head of division
Dr. Michael Österlund
Fusion Diagnostics
Professor Göran Ericsson
Nuclear Reaction Research
Professor Stephan Pomp
Total numbers of employees
50
Nuclear Fuel Diagnostics
and Safeguards
Dr. Peter Jansson
Ion Physics
Dr. Daniel Primetzhofer
Internal collaboration with
the Divisions of Materials
Theory and Materials
Physics
Teaching and education
Undergraduate teaching
We are responsible for three education programs:
- “Civilingenjörsprogrammet i energisystem”
- “Högskoleingenjörsprogrammet
i kärnkraftteknik”, KKI
- “Kandidatprogrammet i fysik”
- Contract education
UU provides the nuclear industry with
contract education courses through NANSS.
Teaching objectiveso Provide as many Masters’ Engineering students as possible with
nuclear technology relevant courses. Allow for specialisation in
nuclear engineering.
o Development of the Bachelors’ Engineering programme in nuclear
engineering.
o Provide supervision for students whishing to do a diploma work within
nuclear technology.
o Provide the industry with relevant further education
Teaching and education at UU
Problems
The number of students decreasing (down approx. 10%)
The Nuclear Power Engineering programme, KKI, will most likely be put
on hold.
The shaky funding of nuclear research implies a risk of shortage of
academic teachers leading to a drastically decreased capacity. This is of
national concern:
• It is not unlikely for a political turn regarding nuclear power.
• Regardless of this, nuclear competence will be needed for decades to
come.
Possibilities
• A frustrating fact: The student’s interest for nuclear technology as such
is intact but the don’t consider nuclear sector as an attractive
employer.
• Ongoing work to implement courses within the KKI programme into
the contract education programme by adapting to industrial needs by
modularisation, e-learning (possibly in collaboration with Chalmers
and KTH) etc.
• Ongoing dialogue with the political sphere. There is a clear
understanding of the imminent problem of competence supply.
Teaching and education at UU
Magnus Ahnesjö: Tomographic reconstruction of subchannel void measurements
of nuclear fuel geometries.
Joel Blomberg: Sensitivity study of control rod depletion coefficients.
Daniel Constanda: Control Rod Effect at Partial SCRAM - Upgrade of Plant Model
for Forsmark 2 in BISON After Power Uprate.
Henrik Liljenfeldt: Applying fast calorimetry on a spent nuclear fuel calorimeter.
Tobias Lindström: SPARC fast reactor design Design of two passively safe
metal-fuelled sodium-cooled pool-type small modular fast reactors with
Autonomous Reactivity Control.
Gjertrud Louise Langaas: Measurements of radioactivity in plant and soil
samples taken near a nuclear power plant.
Moa Skan: Analysis of the neutron albedo’s influence on TIP deviations in
Forsmark 1.
Joakim Nordlander: Evaluation of the dimensional stability in the PWR
assemblies in Ringhals.
Sebastian Leo Eile Svanström: Load following with a passive reactor core using
the SPARC design.
Mattias Åkerman: Improved peaking factors with radial enrichment distribution for
PWR fuel assembly.
SKC relevant Diploma Work 2015-
16
Fission group
Nuclear
safeguards
Nuclear fuel
diagnostics
Back-end fuel
characterization
Gen IV
systems
Responsible:
Sophie Grape
Responsible:
Peter
Andersson
Responsible:
Peter Jansson
Responsible:
Carl Hellesen
Nuclear Safeguards
• Active and passive interrogation
techniqes for verification of fuel
properties
• Using MVA-techniques to develop
models for verification of spent fuel
properties based on high-
dimensional measured data3He
Pb
W
H2O
SFA
NG
polyethylene
Cd
liner
Nuclear Safeguards Modeling and measurement of Cherenkov light
Presentation tomorrow 10:50 in Uppland
Erik Branger, Uppsala University, Predicting the Cherenkov light intensity of irradiated
nuclear fuel assemblies in wet storage for nuclear safeguards purposes.
• The DCVD is an IAEA-approved
technique for partial defects
verification.
• Partial defects are identified by
measuring Cherenkov-light
intensities that are lower than
predicted.
• Thus, accuracy of predictions is
essential!
Proposal of LOCA rod inspection using gamma tomography was first
presented in SKC symposium in Sigtuna 2015.
Fuel diagnostics
Slide from last
year’s symposium
Results presented
at TOP fuel 2016
Presentation tomorrow 10:30 in Lappland
Peter Andersson, Uppsala University, Nuclear fuel diagnostics within MÅBiL in
collaboration with the Halden Reactor Project
Outer part of
lateral
neutron
shield with
Neutron
channel
[C. JAMMES et al,
Nuclear Engineering
and Design, 2014]
Gen IV reactor systems
Developing detectors for SFR in
colaboration with CEA.
• In-vessel ex-core detectors (Fission
chambers)
• In-core detectors (Self-powered
detectors)
Recent results
- Detectable signature in fission
chambers following withdrawal of outer
control rod
- In-core detectors needed for precise
knowledge of location of perturbations
V. Verma, P. Filliatre, C. Hellesen, S. Jacobsson Svärd, C. Jammes, Neutron flux
monitoring with in-vessel fission chambers to detect an inadvertent control rod
withdrawal in a sodium-cooled fast reactor, Annals of Nuclear Energy, Volume 94,
August 2016, Pages 487-493, ISSN 0306-4549,
http://dx.doi.org/10.1016/j.anucene.2016.04.019.
Reaction group
Microscopic
measurements
Nuclear reaction
modeling
Application simulations
and
uncertainty quantificationfeedback
Nuclear Data underpin all of Nuclear
Science and Technology!
Microscopic
measurementsMicroscopic measurements (cross sections and fission yields)
NFS, France (1+1 PhD)• Precision measurements of cross sections, e.g.,
235U(n,f) and 238U(n,f) vs. cross section standards
• Measurement of neutron-induced light-ion production from various targets in the energy range 5 – 200 MeV
IGISOL, Finland (2 PhD)• Measurement of independent fission yields in
thermal and fast neutron spectra
IRMM, Belgium• Measurement of reference cross sections and
neutron emission from fission
partly financed by VR
supported by SSM and
the EU via CHANDA
supported by VR and
the EU via CHANDA
supported SSM and the
EU via CHANDA
Microscopic
measurementsMicroscopic measurements (cross sections and fission yields)
NFS, France (1+1 PhD)• Precision measurements of cross sections, e.g.,
235U(n,f) and 238U(n,f) vs. cross section standards
• Measurement of neutron-induced light-ion production from various targets in the energy range 5 – 200 MeV
IGISOL, Finland (2 PhD)• Measurement of independent fission yields in
thermal and fast neutron spectra
IRMM, Belgium• Measurement of reference cross sections and
neutron emission from fission
Nuclear
reaction
modeling
Nuclear reaction modeling
improved modeling
of fission yields
GEF + TALYS = true from thermal to fast
energy range
(inventory; fuel cycle,…)
+ ISOMERIC YIELD RATIOS…
TENDL och Total Monte Carlo (TMC)
0.98 1.00 1.02 1.05 1.07
20
40
60
80
100
Experimentell data:kalibrering
e.g. safety parameter
Nuclear data
codes
Experimental data for
calibration
Application
Simulations: reactor
and depletion codes
Result
MÅBiL
Running projects
Chalmers• Aneta Sajdova - ”Accident tolerant Uranium Nitride fuel”
• Kristina Lindgren - ”Ageing of RPV Steel - An Atom Probe Tomography Study”
KTH• Elin Toijer - "Combined experimental and theoretical investigation of
underlying phenomena for irradiation assisted stress corrosion cracking"
Uppsala University• Petter Helgesson - ”Improved nuclear data for material damage applications
in LWR spectra”
• Erki Metsanurk - ”ICEWATER – Irradiation Corrosion Experiment Water”
• Maciej Kaplan - “Amorphous thin films for coatings”
• Peter Andersson - “Nuclear Fuel Diagnostics within MÅBiL in collaboration with the Halden Reactor Project”
MÅBiL
Questions of interest
1. Status: Do the projects fulfill the goals according to plan?
a) Research results
b) Economy
2. Future 1: When are the current projects expected to end?
3. Future 2: In the coming SKC agreement it is, among others, expected a continuous collaboration between the universities:
a) Is MÅBiL the road forward in this respect?
b) Can MÅBiL comprise interdisciplinary research between materials sciences and more classical nuclear technology subjects?
MÅBiL
Questions of interest
Do the projects fulfill the goals according to plan?
Research results.
Overall, all projects have fulfilled the scientific goals so far.
Economy
No project has exceeded the budget.
MÅBiL
”Accident tolerant Uranium Nitride fuel”
Sol-gel beads with corrosion resistant elements have been manufactured. This kind of material has never before been made and thus it will need extensive characterisation, which is ongoing.
In principle the underpinning idea is that these added elements will migrate to the phase boundaries and there produce a thin layer of protective oxide which will prevent the nitride from reacting. This part will be investigated in detail later in the project.
MÅBiL
Nuclear Fuel Diagnostics within MÅBiL in collaboration with the HaldenReactor Project”
a. Methodology for fuel diagnostics have been developed.
b. New and previous HRP experiment have been analysed.
c. New measuring methods have been developed for studying rod-wise FGR and fuel reallocation within LOCA test rods.
ATF materials have not been studied simply depending on that such materials have not yet been irradiated at HRP. However, the developed methodologies are feasible for studying the ability for ATF to contain volatile fission products.
MÅBiL
”Ageing of RPV Steel - An Atom Probe Tomography Study”
Application of atom probe tomography (APT) to study clusters/precipitates forming in RPV steels under irradiation. Materials irradiated in Halden (up to 80 years of equivalent dose) have been compared to identical material from surveillance testing. The results show that there are no "late blooming precipitates"; the NiMnSi(Cu) precipitates grow with increasing fluence, but they do not change in nature.
The effect on embrittlement seems to have a weak dependency on flux and the hardness increases linearly with fluence, after a fast increase early in life. Thermal aging has also been studied. It has been found that the welds of the pressurizer becomes embrittled due to the formation of Cu precipitates on dislocations.
MÅBiL
"Combined experimental and theoretical investigation of underlying phenomena for irradiation assisted stress corrosion cracking"
1. The grain boundary cohesion as function of radiation damage is in the process of being modelled. Elin has studied segregation profiles for phosphorous in a model material (fcc Ni) and is adding Fe, Cr and point defects to describe local chemical effects (in the solid) and interplay with radiation induced defects for the weakening of the grain boundaries.
2. She has also completed a first study of the reactivity in water of 304 stainless steel .
3. The project group has started to make a detailed experimental set up for testing if the effect of chemistry can be isolated from that of radiolysis in the crack tip region (see E. Toijer's presentation).
MÅBiL
”Improved nuclear data for material damage applications in LWR spectra”
The project has been very successful. Among others, new data for Ni-59 has been obtained and new methods for handling uncertainties in transient calculations connected to uncertainties in nuclear data have been developed, all according to plan. The project’s centre has been shifted somewhat towards structural materials.
In addition to the Ph.D. Student, a postdoc, Augusto Hernadez, funded by UU, is contributing to the project.
MÅBiL
”ICEWATER – Irradiation Corrosion Experiment Water”
Although in nature ICEWATER is an experimental project, a considerable effort has been put into understanding the theoretical aspects behind IASCC and how would ICEWATER contribute to the existing knowledge.
• Designed and assembled an apparatus capable of heating flowing water at 130 bars of pressure up to 320 °C.
• Performed irradiation experiments in order to assess the buildup of activity in stainless steel foils in order to select the possible ranges of energies and currents for forthcoming experiments.
• Design of a 3-D model of a test cell. With it is possible to stress the sample either with constant or slowly varying load. The next step is to manufacture and assemble the cell in collaboration with Sandvik and KTH.
MÅBiL
“Amorphous thin films for coatings”
MoSiZr alloys have been studied and to gain knowledge of how the composition affects the crystallisation temperature, which enables further improvement of thermal stability. Crystallisation temperatures of the MoSiZralloys were investigated by heat treatments in vacuum and ex-situ X-ray diffraction and X-ray reflectivity analysis.
The highest thermal stability of the alloys was exhibited by Mo48Si48Zr4, Mo43Si50Zr7, Mo50Si40Zr10 and Mo45Si43Zr12, they remained amorphous after heat treatment at 1073 K. The resulting crystalline phases are Mo3Si, Mo5Si3 and ZrO2. Oxidation of Zr in the alloys is present only when the Zrcontent is ≥10 at%, crystallisation is otherwise mainly driven by formation of Mo3Si.
Further improvement of the thermal stability is possible by introducing new alloying elements at the cost of those that promote crystallisation. Keeping the content of Zr below 10 at% is of great importance to prevent oxidation.
MÅBiL
Questions of interest
Future 1: When are the current projects expected to end?
”Accident tolerant Uranium Nitride fuel”: Lic. Spring 2017, Ph.D. Autumn 2019.
”Ageing of RPV Steel - An Atom Probe Tomography Study”. Ph.D. Spring 2019.
"Combined experimental and theoretical investigation of underlying phenomena for irradiation assisted stress corrosion cracking“: Ph.D. Nov 2019.
”Improved nuclear data for material damage applications in LWR spectra”: Planned dissertation 2018-05-30.
”ICEWATER – Irradiation Corrosion Experiment Water”: Ph.D. 2017.
“Amorphous thin films for coatings”: T.B.D.
Peter Andersson - “Nuclear Fuel Diagnostics within MÅBiL in collaboration with the Halden Reactor Project”: Project ending spring 2017 with a planned continuation.
MÅBiL
Questions of interest
Future 2: In the coming SKC agreement it is, among others, an expectancy on continuous collaboration between the universities: Is MÅBiL the road forward in this respect?
MÅBiL is the first of its kind. Collaboration all over the scope (sometimes more, sometimes less). Generally seems to work adequately but we can do better in a MÅBiLII so the answer is “yes”.
MÅBiL has been a valuable stepping stone for creating international collaborations e.g. within IAEA CRP inom Primary Radiation Damage Cross Sections.
Within all projects, various methodologies have been developed that would give MÅBiLII a flying start. This forms another rationale for continuing the idea of MÅBiL.
MÅBiL
Questions of interest
Future 2: In the coming SKC agreement it is, among others, an expectancy on continuous collaboration between the universities: Can MÅBiLII comprise interdisciplinary research between materials sciences and more classical nuclear technology subjects?
MÅBiL tries to address this issue to some extent. But only parts of reactor physics, nuclear chemistry, safety & security, … are involved explicitly.
On the other hand, there is collaboration between for example Chalmers and UU in reactor relevant research. How to take care of such collaborations?
MÅBiL
Issues
All projects are not adequately funded implying either part-time working Ph.D. students and/or supervision paid by faculty money, which leads to delays. In addition:
• ”Accident tolerant Uranium Nitride fuel”
On-going discussion with Westinghouse regarding patenting of results => risk for additional delay.
• “Amorphous thin films for coatings”
The project is recently manned with a new student, waiting for a go/no go decision.
• The requirement that all publications shall pass the industrial partners prior to publishing has obviously not reached all project leaders. We must do better here.
• The work with quarterly reports is put on top of exponentially increased volume of administrative duties => less time for thoughts and supervision.
MÅBiL
