SINBAD ABSTRACT NEA-1517/75
Winfrith Water/Iron Benchmark Experiment (ASPIS-PCA REPLICA)
1. Name of Experiment:
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Winfrith Water/Iron Benchmark Experiment (PCA Replica)
2. Purpose and Phenomena Tested:
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Determination of neutron spectra and detector reaction rates at different
depth in the ASPIS facility in a water/iron shield reproducing the ex-core
radial geometry of a Pressurized Water Reactor (PWR).
A replica of the Oak Ridge PCA experiment with a highly enriched fission
plate in place of the core source. The cross-sectional area of the fission
plate was identical to that of the PCA source.
3. Description of the Source and Experimental Configuration:
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The PCA-REPLICA duplicated precisely the Oak Ridge PCA 12/13 configuration
(12 and 13 cm of water respectively between the core and thermal shield and
between the thermal shield and the pressure vessel-RPV) with the exception
that the reactor source was replaced by a thin fission-plate to provide a
well characterized neutron source. The fission-plate was irradiated by
the NESTOR reactor at UKAEA-Winfrith (30 kW max. power) through a graphite
thermal column of total thickness 43.91 cm, in the ASPIS shielding
facility.
The REPLICA shielding array was arranged in a large steel tank (square
section; side 180.0 cm) filled with water and surrounded by a thick
concrete shield. After the first water gap (12.1 cm), there was the
stainless steel thermal shield (TS) simulator (5.9 cm thick) and the
second water gap (12.7 cm). Then the mild steel RPV simulator (thickness
T = 22.5 cm) was located and tightly connected with a void box made of a
thin layer of aluminium, simulating the cavity (thickness = 29.58 cm)
between the RPV and the biological shield in a real PWR.
4. Measurement System and Uncertainties:
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The detectors used were:
Detector Diameter Systematic Random Error
(mm) Error (%) (1 sigma) (%)
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Mn-55(n,gamma) 12.7 1.5
Rh-103(n,n') * 3.0 1-4
In-115(n,n') * 2.0 0.9-1.5
S-32(n,p) * 4.0 1.3-1.9
U-235(n,f) * 1 3
SP-2 counter 40.0 (internal diam.)
NE213 Spectr. spherical,vol=3.5 ml
----------------------------------------------------
* thin foils, can be neglected in the calculations.
Hydrogen-filled proportional counters with gas fillings of approximately
0.5, 1.0, 3.0, and 10.0 atmospheres were used in combination to cover the
energy range from 50.0 keV to 1.2 MeV. Neutron fluxes between 1.0 and 10.0
MeV were determined with a NE213 organic liquid scintillator.
5. Description of Results and Analysis:
-----------------------------------
Threshold detectors were located at 10 different positions: in the water
gaps 1.91, 7.41, 12.41, 14.01, 19.91, 25.41, 30.41 cm from the fission
plate (Rh measurements only) and at 1/4 and 3/4 thickness of the RPV
and in the void box (Rh, In, S).
Spectral measurements were performed at two positions: at 1/4 thickness
of the RPV and in the void box.
The spectra were unfolded by the RADAK [6] computer code.
At least 2-D calculational model has been recommended by the authors.
Monte-Carlo code McBEND, TRIPOLI and 2-D discrete ordinates transport code
DOT-3.5 have been used in refs. [1], [3] and [9].
6. Special Features:
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None
7. Author/Organizer
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Experiment and analysis:
J. Butler, M.D. Carter, I.J. Curl, M.R. March, A.K. McCracken, M.F. Murphy,
A. Packwood
AEA Technology
WINFRITH, Dorchester
Dorset DT2 8DH
UK
Compiler of data for Sinbad:
I. Kodeli
OECD/NEA, 12 bd des Iles, 92130 Issy les Moulineaux, France
Reviewer of compiled data:
M. Pescarini(*), S. Zheng(**)
(*) ENEA, Via Don Fiammelli 2, 40129 Bologna, Italy
(**)CEA-Saclay/DMT/SERMA/LEPP, 91191 Gif-sur-Yvette CEDEX, France
8. Availability:
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Unrestricted
9. References:
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[1] J. Butler, M.D. Carter, I.J. Curl, M.R. March, A.K. McCracken, M.F.
Murphy, A. Packwood, The PCA Replica Experiment PART I, Winfrith
Measurements and Calculations, AEEW-R 1736 (1984)
[2] J. Butler, The NESTOR Shielding and Dosimetry Improvement Programme
NESDIP for PWR Applications, PRPWG/P(82)5, Internal UKAEA Document,
(1982)
[3]A) M. Pescarini, DOT 3.5-E (DOT 3.5-E/JEF-1) Analysis of the PCA-Replica
(H2O/Fe) Shielding Benchmark for the LWR-PV Damage Prediction,
ENEA Technical Report, RT/INN/90/21 (1990)
and,
B) M. Pescarini, ENDF/B VI Iron Validation on the PCA-Replica (H2O/Fe)
Shielding Benchmark Experiment, ENEA Technical Report, RT/INN/94/11.
[4] M. Pescarini, PCA Replica Shielding Benchmark: Final Comparison of the
Validations of the ENDF/BVI and JEF-2.1 Iron Cross Sections,
JEF Working Group Meetings, JEF-DOC-392 (1992)
[5] M.D. Carter, I.J. Curl, P.C. Miller, A. Packwood, Light-Water
Reactor Radial Shield Benchmark Studies of the NESTOR Shielding
and Dosimetry Improvement Programme (NESDIP), Reactor Dosimetry:
Methods, Applications, and Standardization, ASTM STP 1001,
Harry Farrar IV and E.P. Lippincott Editors, ASTM, Philadelphia
[6] M.J. Grimstone, The RADAK User's Manual, AEEW-M1455 (1976)
[7] McELROY W. N. (Ed), LWR Pressure Vessel Surveillance Dosimetry
Improvement Programs: PCA Experiments and Blind Test,
HEDL-TME 80-87, R5 (NUREG/CR-1861), July 1981
[8] STALLMANN F. W., Reactor Calculation Benchmark PCA Blind Test Results,
ORNL/NUREG/TM-428 (NUREG/CR-1872), January 1981
[9] J. C. Nimal, S. H. Zheng, Rapport DMT 94/1616, CEA-Saclay
[10] P. C. Miller, A Review of LWR Pressure Vessel Dosimetry and Associated
Shielding Studies, Proceedings, 7th International Conference on Radiation
Shielding, Sept. 12-16, 1988, Bournemouth, UK, Vol.1, p.37.
10. Data and Format:
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Filename Size[bytes] Content
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1 repl-abs.htm 11.637 This information file
2 repl-exp.htm 34.855 Description of Experiment
3 tripoli4rep_r.inp 24.573 Input for TRIPOLI4 fast neutron calculations (by C. Jouanne)
4 tripoli4rep_t.inp 27.961 Input for TRIPOLI4 thermal neutron calculations (by C. Jouanne)
5 tripoli3rep.inp 11.232 Input for TRIPOLI3 calculations (by S.H.Zheng)
6 REPL-XZ.INP 29.728 Input data for DOT-3.5 (X,Z) calculations (by M. Pescarini)
7 REPL-YZ.INP 29.318 Input data for DOT-3.5 (Y-Z) calculations (by M. Pescarini)
8 REPL-Z.INP 25.790 Input data for DOT-3.5 Z calculations (by M. Pescarini)
9 REPL-1V.TIF 47.024 Fig. 1: NESTOR Neutron Source Reactor (high quality)
10 REPL-2V.TIF 35.034 Fig. 2: ASPIS Shielding Facility (high quality)
11 REPL-3V.TIF 15.834 Fig. 3: REPLICA Layout of the 12/13 Configuration (high quality)
12 REPL-4V.TIF 18.394 Fig. 4: Detail of the REPLICA Fission-plate (high quality)
13 REPL-5AV.TIF 9.326 Fig. 5a: Co-ordinate System (high quality)
14 REPL-5BV.TIF 80.792 Fig. 5b: Mn Foil Measurements (high quality)
15 REPL-6V.TIF 77.104 Fig. 6: Fuel Tablet Arrangement in a Fission Plate Element (high quality)
16 REPL-1V.gif 26.090 Fig. 1: NESTOR Neutron Source Reactor (preview)
17 REPL-2V.gif 21.736 Fig. 2: ASPIS Shielding Facility (preview)
18 REPL-3V.gif 11.126 Fig. 3: REPLICA Layout of the 12/13 Configuration (preview)
19 REPL-4V.gif 13.751 Fig. 4: Detail of the REPLICA Fission-plate (preview)
20 REPL-5AV.gif 6.860 Fig. 5a: Co-ordinate System (preview)
21 REPL-5BV.gif 15.052 Fig. 5b: Mn Foil Measurements (preview)
22 REPL-6V.gif 14.212 Fig. 6: Fuel Tablet Arrangement in a Fission Plate Element (preview)
23 REP_1.pdf 2.708.595 Reference
24 REP_3A.pdf 2.665.843 Reference
25 REP_3B.pdf 1.392.429 Reference
26 JEF_392.pdf 1.307.352 Reference
27 REP_9.pdf 659.402 Reference
28 aspis_0.pdf 608.178 Reference
29 radak.pdf 1110.016 Reference
Figures describing the geometry of the experiment are included in
TIFF4 image and GIF (preview) format.
TABLES:
1. Fission Product Activity at Certain Positions in the Fission Plate
2. Axial Variation of the Mean Fission-Rate Profile
3. Source Distribution in the 0.6 cm Thick Fission Plate
4. Cylindrical Representation of Fission-Source
5. Dimensions and Materials in PCA-REPLICA
6. Chemical Analysis of the REPLICA Materials
7. Investigation of the Al Plate Bowing
8. Centreline Activation Measurements: Rh-103, In-115, S-32
9. Fluxes of NE213 Spectrometer
10,11. Activation Measurements on Horizontal Axis: Rh-103, S-32
12. Cosine Fits
13. Estimation of NESTOR Background
14. Activation Measurements on Horizontal Axis: Mn-55
SINBAD Benchmark Generation Date: 1995
SINBAD Benchmark Last Update: 04/2006