Keeping Track of Nuclear Fuel in Reprocessing
Submitting Institution
Newcastle UniversityUnit of Assessment
Mathematical SciencesSummary Impact Type
TechnologicalResearch Subject Area(s)
Mathematical Sciences: Statistics
Summary of the impact
The Thermal Oxide Reprocessing Plant (THORP) at Sellafield in Cumbria has
20% of the world's current annual nuclear reprocessing capacity.
Statistical methods developed in Newcastle during commissioning of THORP
are integral to the nuclear material accountancy systems that are used in
all stages of reprocessing. Since 2008 a Newcastle volumetric calibration
system has been the only means of determining input into the plant.
Regulatory approval of the system has ensured that THORP has been able to
operate throughout the REF period, that customer costing has been
accurate, and that the plant has complied with international standards for
the close control of nuclear materials.
Underpinning research
The underpinning methodology for a volumetric system was developed by
Henderson at Newcastle in 1993-1995, generalised in 1995-2000 in
co-operation with McKnespiey (Newcastle) and Morton-Jones (Lancaster) and
developed further with THORP operators British Nuclear Fuels Ltd (BNFL)
from 2005. Recalibration was carried out in 2009/10 by Henderson in
collaboration with Chater (BNFL, now Sellafield Sites) and Clarke
(National Nuclear Laboratory). The methods have been on-going throughout
the 2008-2013 period.
Operators and regulators use material accountancy methods to help
safeguard against accidental or illicit diversion of nuclear materials.
This requires highly accurate monitoring of all movements of nuclear
material and regular inventories of storage. When, as at THORP, the
materials are held and transferred in dissolved form, amounts of material
can be estimated through a combination of sampling, chemical analysis, and
either weight or volume determination, all of which are subject to error.
A major statistical challenge during initial calibration is to determine
the relationship between level and volume of liquor in a closed vessel
containing significant interior pipework. The relationship is used to
convert level measurements during operations to volume and in turn mass
estimates of nuclear materials.
In generic statistical terms, volumetric calibration forms an inverse
problem involving longitudinal data analysis with errors in variables. An
unknown relationship v=g(l) exists between volume and level in a vessel.
The function g(.) is continuous but at a finite but unknown number of
points it is not differentiable. Smooth segments between discontinuities
in first derivative may be linear or non-linear. During commissioning, p
calibration runs are performed, in which a vessel is filled with measured
aliquots of water from low to high volume, with ni aliquots in
run i. Data (Vij, Lij) are available (i=1,...,p,
j=1,...,ni) subject to correlated error in Vij and
heteroscedastic error in Lij. The purpose is first to estimate
g without bias for all l, and second to describe the associated error
structure. Given a future measurement L0, also subject to
error, a prediction V(L0) is required together with a
prediction interval.
The first challenge was design of calibration runs. Both volume and level
are subject to measurement error. In reference [P1], theoretical
expressions for mean square error were derived for competing methods. A
technique based on in-tank density estimation was recommended on the
grounds of robustness. This technique has been taken up by BNFL and
continues to be used. In reference [P4] the stability of differential
pressure measurements was studied, with a dynamic modelling approach
recommended. A generic methodology paper [P6] shows that generalised least
squares can be much less robust than ordinary least squares in the
presence of measurement error, using calibration as an illustration.
The next decision was on aliquot sizes and number of runs. The first run
begins with an empty vessel. Vessels cannot later be completely emptied:
an unknown heel remains. Further, once active liquors are added to the
vessel then access becomes impossible. Each calibration run is expensive
(vessel capacity is up to 35 tonnes and a single run can take several
days) meaning the number of runs needs to be limited. An expression for
mean square error for the appropriate class of problem was derived in
[P2].
The main methodology developed for fitting volume/level relationships was
an early use of reversible jump Markov chain Monte Carlo [P3, P5]. A
Bayesian approach was appropriate because prior (but unreliable)
information from vessel design drawings is available. The underlying model
for cross-sectional area is piecewise constant, leading to a piecewise
linear relationship between level and volume, with prior information for
slope changes. The Newcastle calibration methods were used during
commissioning to calibrate over 100 process vessels within the THORP
plant.
The calibration methods used bespoke Splus software written by Henderson
and later developed into a commercial package based on the reversible jump
methodology of Paul McKnespiey [P5], whose Newcastle PhD was partially
funded by BNFL. The package was bought by Westlakes Research Institute for
£45,000.
Recalibration of weighing systems is carried out periodically at THORP,
using certified weights sequentially added to load systems. Recalibration
of volume systems is more problematic; however, following necessary
decommissioning of the weighing systems a bespoke validation analysis was
undertaken in 2009/10 [E2, Section 5 below].
References to the research
(ESARDA is the refereed proceedings of the biennial European
Safeguards conference, the primary communication method for scientific
developments in the area).
[P1] Henderson, R., McKnespiey, P.N. and Temple, A. (1995). The
volumetric calibration of tanks: design of trials. ESARDA, 17, 365-369.
[P2] McKnespiey, P.N. Henderson, R. and Temple, A. (1995). Volumetric
calibration: use of in-tank density determination. ESARDA 17, 371-375.
[P3] Henderson, R., Temple, A. and McKnespiey, P. (1997). Computer
intensive inference for calibration curves: experience at BNF THORP.
ESARDA 19, 753-758.
[P4] Morton-Jones, A., Henderson, R., Hunt, B. and Binks, K. (1999).
Optimal control of pressure measurements during volumetric calibration.
ESARDA, 21, 285-289.
[P5] Henderson, R., Morton-Jones, A. and McKnespiey, P. (2000).
Reversible jump MCMC for volumetric calibration. Journal of the Royal
Statistical Society, Series C (Applied Statistics), 49 (4), pp. 563-576.
ISSN 1467-9876 [* Key reference].
[P6] Morton-Jones, A. and Henderson, R. (2000). Generalized least squares
with ignored errors in variables. Technometrics, 42(4), pp.366-375. DOI:
10.1080/00401706.2000.10485709. (American Society for Quality and the
American Statistical Association)
Details of the impact
The amount of nuclear material transferred into and out of the THORP
nuclear reprocessing plant in Cumbria is determined through the vessel
calibration methodology developed in Newcastle and adopted by BNFL. THORP
has the capacity to reprocess 1200 tonnes of nuclear fuel per year, which
is 20% of the world's total current annual reprocessing capacity [E1].
Since 2008 the amount of nuclear material input into the plant has been
determined exclusively through the level/volume methodology developed in
Newcastle. Our methods have ensured that the plant can comply with
regulator's requirements and has been able to operate throughout the REF
period.
Originally a dual system (weight or level/volume) provided built-in
redundancy for nuclear materials accountancy. In 2005 a pipe from a
receipt vessel fractured in the containment area. Operations were
suspended until 2008 and since restart only the level/volume systems have
been available for determination of nuclear receipts. These rely entirely
on the calibration methodology developed in Newcastle. The level/volume
receipt systems were revalidated by Henderson and industry colleagues in
2009/10. Confidence in the systems was confirmed [E2] and operations at
THORP have been allowed to continue.
1. Safety and environmental impacts
Close control of nuclear material is important to prevent the adverse
safety and environmental impacts that would follow accidental release of
radioactive material.
The 2005 leak was detected through nuclear material accountancy based on
the vessel calibrations carried out using the Newcastle methodology. In
[E3], Section 33, the Health and Safety Executive stated that "The HSE
investigation found that it was not the installed leak detection systems
that led to the discovery of the leak. It was the analysis of nuclear
materials accountancy (NMA) discrepancies at the end of several fuel
shearing campaigns that led to the detailed investigations.... and
subsequently to the discovery of the leak."
2. Security impacts
Over 6000 tonnes of spent nuclear fuel from nine countries have passed
through THORP calibrated vessels since commissioning. Close control of
this fuel is extremely important for quickly identifying any security
breaches or misuse of nuclear materials. The International Atomic Energy
Agency (IAEA) is charged with monitoring civil programmes in order to ``establish
and administer safeguards designed to ensure that special fissionable
and other materials ... are not used in such a way as to further any
military purpose" [E4].
One aspect of this safeguards work is material accountancy, by which
records of movements of material are kept and regular inventories taken.
The main receipt vessels at THORP are the Head End Accountancy Tanks
(HEATs), which are used for input determination. The main issue vessels
for plutonium product (HARPs) are used for output determination. Given
their importance, the HEAT and HARP vessels were designed to have dual
accountancy systems: a primary system based on weight and a secondary
system based on volume/level. Highly accurate weighing systems were
installed and calibrated using fairly straightforward models developed in
Newcastle during 1993-1994. The more problematic and statistically
challenging volumetric systems were installed, calibrated and recalibrated
in 2009/10 using models described in the underpinning research above.
Throughout, the European Atomic Energy Community (Euratom), which acts for
IAEA in Europe, approved the methods and results [E5].
In [E6], the THORP materials custodian says "The volumetric
calibrations of the 12 main process vessels, which are also key
measurement points for accountancy purposes, continue to be used on a
daily basis and to pass the daily revalidation exercises". The
Newcastle work is key to this.
3. Commercial costing impacts
THORP is one of only three commercial light water reactor fuel
reprocessing plants in the world [E7]. Customers are charged according to
the quantities of material received, as measured in the receipt vessels,
and THORP charges purchasing customers according to the amount of product,
as measured at issue. The material of main interest is plutonium, which is
generated during reprocessing of spent nuclear fuel. Extremely accurate
measurement is necessary, with relative standard deviations of the order
of 0.1% for plutonium being required. The Newcastle calibrations delivered
this accuracy. Bias in the measurement system can lead to commercial
charges measured in millions of pounds. Exact charges and costs are
commercially confidential.
In summary, our volumetric system continues to be the sole means of
determining transfers of nuclear materials into or out of THORP.
Operations could have not have continued after 2008 without regulatory
approval of these accurate and reliable accountancy systems.
Sources to corroborate the impact
[E1] "Reprocessing Plants, Worldwide", European Nuclear Society
Encyclopaedia (2012).
http://www.euronuclear.org/info/encyclopedia/r/reprocessing-plants-ww.htm,
[accessed 04/09/2013]
[E2] Clarke, C.G, Chater, S.P. and Henderson, R. (2010). "Review of
HEAT A liquor measurement performance using volume density system".
Sellafield Ltd Technical Report TTC/10/707 (N).
[E3] "Report of the investigation into the leak of dissolver product
liquor at the Thermal Oxide Reprocessing Plant (THORP), Sellafield,
notified to HSE on 20 April 2005", Health and Safety Executive
(2007), available at: http://www.hse.gov.uk/nuclear/periodic-safety-review/thorp.htm.
[accessed 04/09/2013]
[E4] "IAEA Statutes Article III.A.5", International Atomic Energy
Agency (2013) http://www.iaea.org/About/statute.html,
[accessed 04/09/2013]
[E5] Corroboration from the Head of Nuclear Fuel Cycle Analysis Section,
Division of Information Management, Department of Safeguards,
International Atomic Energy Agency & former Euratom inspector.
[E6] Corroboration from the Material Custodian, Thorp Chemical Plants,
Sellafield Ltd, March 2011.
[E7] "Processing of Used Nuclear Fuel" (2012) World Nuclear
Association, http://www.world-
nuclear.org/info/inf69.html, [accessed 04/09/2013]