ML20246B364
| ML20246B364 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 06/28/1989 |
| From: | Newton T WORCESTER POLYTECHNIC INSTITUTE, WORCESTER, MA |
| To: | Michaels T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8907070309 | |
| Download: ML20246B364 (18) | |
Text
-
Mechanical Engineering Department 100 Institute Road Worcester, MA 01609-2280 WORCESTER (503)s31 5000 0gt INSTITUTEA PotyrECHNIC FAX:(508) 831-5483 June 28, 1989 50-134 Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Re: License No. R-61
Dear Mr. Michaels:
Enclosed please find a copy of the report on the conversion of the Worcester Polytechnic Institute Nuclear Reactor to low enriched uranium, as required by the conversion order of 12 September,1988.
Additionally, shipment of the HEU fuel from WPI to the Savannah River 15 - 19, 1989, but was not Facility was originally scheduled for May completed due to the inability of the Savannah River Facility to receive fuel as originally scheduled.
At the present time, no shipping window shipping window during that week.is available during 1989, which create annual reactor maintenance (nonna11y scheduled during the sumer), since we I will cannot unload the LEU core with HEU fuel in the fuel storage racks.
keep you informed on this matter.
Please let me know if I can provide you with further information.
Sincerely, i
h%.
~
Thomas H. Newton, Jr.
- Director, Nuclear Reactor Facility THN:ama Prof. John A. Mayer, Jr.
cc:
A020 l
8907070309 890628 f,DR ADOCK 03000g34 PDC 1
l
Repo'rt on Conversion of the Worcester Polytechnic
'i
-i
. Institute Nuclear Reactor Facility to-Low-Enriched Uranium j
I. INTRODUCTION l
On 20 December 1988, WPI received 28 LEU 18 plate aluminide elements for use in the reactor core, replacing HEU fuel unloaded on 16 December 1988.
Initial loading began on 27 December 1988, with l
initial criticality being achieved on 29 Decem'oer 1988.
l Testing on the LEU core was performed and the results compared with calce?ctions performed for WPI by Argonne National Laboratory
.i (ANL).
It should be noted that.the ANL calculations were in all cases based on the reference 24 element core shown in Figure 1.
HEU l
measurements were made using the reference core.
It was not*pos-sible, however, to perform LEU measurements with the reference 24
- element core since criticality occurred at a fuel loading of slightly greater than 21 elements.
II. CRITICAL MASS The critical loading for the HEU core was 3.242 kg U-235.
Although no calculations were performed by ANL for HEU critical mass, excess reactivities were very close (see below) to measured values.
The loading at criticality for the LEU core was 3.560 kg U-235 l
(21 elements + 4 plates as shown in figure 2) compared with the ANL calculated 4.000 kg (24 elements).
The reason for this discrepancy is currently under investigation by ANL. The difference between measured and calculated values in and of themselves do not have a significant impact on normal operations or accident conditions. M
-__.a.
n-
a y..
III. EXCESS REACTIVITY Excess reactivity measurements through the 29 years of operation
~
for the HEU fue'l has shown a variation:between 0.23% and 0.26% Akg, ANL calculations show good agreement with a value of 0.29%.
For the 21-1/3 element LEU arrangement, the measured value is 0.16% ak/k. Subsequent ANL calculations show this arrangement to be subcritical by about 2.5%.ak/k. Although the calculations are far from the measured values, measurements show the excess reactivity to be well below the 0.5% technical specification limit.
IV. POWER CALIBRATION After LEU fuel loading was complete, a complete survey of radial and axial neutron flux distribution at about 200W was made using gold foils. Calculations based on this distribution showed that the neutron detectors for power level indication which was set for the HEU core would reed about 26% too high. The initial calibration showed the instrumentation to be reading between 24% and 33% too high. Cadmium covered gold foils were also used to determine if any
' spectral differences existed between LEU and HEU cores, which would affect detecter output for a given flux. These results showed virtually no difference between cores. The original radial position of all detectors remain unchanged in the LEU core.
V.
THERMAL NEUTRON FLUX DISTRIBUTION Average thermal neutron flux distributions were detennined using l
gold foils placed in each element and irradiated during operations of about 200W. The HEU core flux distribution is rhown in Figure 3.
The measured values show good agreement with ANL calculations. LEU core measurements and calculations are shown in Figure 4.
Since the actual measured values are distributed over less fuel than the ANL calculated values, the percent power is naturally higher. Similar trends, however, can be seen between the two values as well as with (
m.
(
e
{
1 the HEU core. The higher LEU measured value at position E-7 is due i
to thermal flux peaking in the partially loaded removable plate element.
]
VI..
CONTROL AND REGULATING BLADE WORTHS The reactivity worths for the regulating blade and four config-urations of control blades are shown below. The LEU measured values are for the 21-1/3 element core,'while all other values are for the 24' element reference core.
. Worths of Blades, Ak/k HEU LEU Regulating Blade Measured 0.4%
0.52%
Calculated 0.7%
0.7%
Blades 1,2 in; 3, R out Measured 3.8%
6.6%
Calculated 6.5%
6.5%
Blades 2,3 in; 1, R out Measured 8.3%
12.2%
Calculated 7.8%
7.7%
Blades 1,3 in; 2, R out Measured 7.2%
9.9%
Calculated 8.2%
8.1%
Blade 2, in; 1,3, R out Measured 2.5%
3.9%
Calculated 3.6%
3.5%
i Although there are some discrepancies between calculated and measured values, the relative worths of different configurations are consistent, showing adequate shutdown worths for any blade config-uration.
Measured differential control blade worths are shown in figures 5 & 6.
Although no calculations were made because of the differing worth values for many different configurations, the measured values i
show the same trends as calculations for the total rod worths for
-A
\\
j
n.
both the LEU and HEU cores. The differences in LEU worth of blades 1-and 2 as compared with total worths values are due to the fact that differential worth measurements were made at different blade config-l urations than total measurements. Measured differential regulating blade worths are shown in figure 7.
Again, the same trends as total worths can be seen.
VII. SHUTDOWN MARGIN The shutdown margin for each of the blades out was measured for both the LEU and HEU cores,.and are shown below. Again,-the LEU measured values are for the' 211/3 element core, while all others are l
. for the 24 element reference core.
Reactivity Worth % o k/k Blade out HEU HEU LEU LEU Measured Calculated Measured Calculated 1
8.3 7.8
-12.2 7.7 2
7.2 8.2 9.9 8.1 3
3.8 6.5 6.6 6.5 These v61ues show reasonably good agreement with ANL calcula-tions and all show the highest worth blade to be No. 3.
All values are well above the 1% technical specifications limit.
VIII. PARTIAL ELEMENT WORTHS The partial element, loaded in position E-7, was loaded with 4 plates when criticality occurred.
Subsequent loadings of one plate each showed a reactivity worth of 0.08% ak/k per plate. ANL calcula-tions made for position F-3 showed a worth of between.06% and.085%
i per plate.
i l L
IX. VOID AND TEMPERATURE COEFFICIENTS Accurate measurements of void and temperature coefficients are
]
difficult. Attempts have been made over the years to introduce voids j
into the core for reactivity measurements and all have shown negative values in the core region. However, the method of introducing voids into the core frequently causes significant reactivity effects in addition to the voiding.
It is even more difficult to extraplate from an individual measurement to an average coefficient for the entire core. Because of these uncertainties, no attempt to verify actual values of coefficient has been made. Small voids can, how-
)
ever, be introduced into the core to verify a negative reactivity j
value.
]
Similarly, attempts have been made to measure the temperature coefficient by heating or cooling the entire pool of water and comparing with the original critical blade positions. These attempts typically take several days to accomplish and do not accurately reflect conditions under which reactivity effects would be seen with changing temperature during operation. A recent measurement for the llEU core gave a value of -5.2 x 10-5 Ak/k F, compared with the ANL calculated - 1.7 x 10-4 ok/k F.
Because of these reasons, as well as the fact that fuel heating has a significant Doppler effect in the i.EU core, it was decided to measure reactivity changes with increasing power to determine the overall temperature coefficient of the LEU core. At 10 kw, the average temperature rise across the core was 5.5 C.
The reactivity change, based on the change in the regulating blade position was A
about -0.05% k/k, giving an overall temperature coefficient of -9 x
-5 ok 10
/k C compared with ANL calculations of -1.7 x 10-4 k/k'C.
-5 ok These are both more nega'tive than the -2 x 10
/k C technical specification limit. The measured value has some uncertainties involved, such as the variation of temperature from measured points.
Any difference in average temperature can change the coefficient signi ficantly. -
V.; :; -
f',
X. INITIAL LEU LOADING The LEU fuel loading br.gan on 27 December,1988 in 2 steps of six elements each and a 1/m plot made to predict the critical config-r urations. Thereafter, fuel was loaded in steps corresponding to L one/ half of the updated estimated critical configuration from the 1/m pl ots. The plots, made for all rods out and ratio of rods in to rods out are!shown in figures 8 and 9.
Figures 10 and 11 show the 1/m plots on a per plate basis during loading steps 6 through 8.
The loading steps are presented below with loading steps 7 and 8 showing total fuel plate loading rather than element loading.
1/m critical predictions Loading Number of Rods out Rods in/
Additional Step Elements Rods out Loading 1
6 2
12 16 27 4
3 16 18 23.5 2
4 18 21 22-1/2 2
5 20 20.8 22 -1 /3 1
6 21 21-1/3 21-1/3 2 plates 7
21 + 2 plates (380p) 382-1/2 382-1/2 1 plate 8
331 plates 382-1/2 381-1/2 1 plate 9
382 plates critical The excess reactivity at 382 plates was measured to be 6 x 10-4 ak/k.
Two plates were later added to increase the excess reactivity to
- 0. '16%.
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