IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
CHILEAN EXPERIENCE WITH SHIPMENT
OF
RESEARCH REACTOR SPENT FUEL
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Contact:
Mr. Juan Klein
Comision Chilena de Energia Atomica
Amunategui 95
Santiago, Chile
Tel.: +56 2 273 1827
Fax: +56 2 273 8723
E-mail:
IAEA/USA Interregional Training Course
Technical and Administrative Preparations Required for Shipment of Research Reactor Spent
Fuel to its Country of Origin
13-24 January 1997
Argonne, IL
Lecture L.13.2
CHILEAN EXPERIENCE WITH SHIPMENT OF
RESEARCH REACTOR SPENT FUEL
presented by
J. Klein and E. Saravia
Chilean Nuclear Energy Commission
Santiago - Chile
1.- Introduction
On May 14, 1996 the Executive Director of the Chilean Nuclear Energy Commission
(CCHEN) received a letter from the Embassy of the United States in Santiago
informing about the decision of the U. S. Department of Energy to accept and
manage in the United States all the spent nuclear fuel listed in the Environmental
Impact Statement (EIS). As stated in the referred document, the fuel, all which
contains uranium enriched in the United States, is to be accepted over a thirteen
year period.
Countries listed in the EIS as developing ones will have the cost of fuel shipments
and management subsidized by the United States. Arrangements will be made through
the Department of Energy Office of Spent Fuel Management.
On May 31, 1996 the CCHEN¥s Executive Director received a second letter
from the Embassy of the United States in Santiago informing of the Record of
Decision (ROD) for an environmental impact statement of a policy to manage foreign
research reactor spent nuclear fuel. Additionally, the letter advised on the
convenience of receiving an assessment team to familiarize reactor operators
with the program, and to gather necessary information and make essential contacts
in advance. A tentative shipment of all eligible South American spent fuel was
planned for August 1996.
On June 10, 1996 a fax was received at CCHEN proposing a U. S. delegation to
visit the RECH-1 research reactor. After the acceptance of CCHEN, the visit
took place on June 21 at La Reina Nuclear Center where the delegation meet with
CCHEN¥s personnel.
On June 27, 1996 the CCHEN¥s Board of Directors approved to participate
in the first shipment of spent nuclear fuel to the United States from South
America. From this date on, two main lines of activities were executed simultaneously:
(i) Negotiations and Management and (ii) Technical Activities.
2.- Negotiations and Management
In order for the CCHEN to carried out the several and most diverse activities
related to negotiations and management of this operation, it was decided to
have a centralized and vertical organization at CCHEN. This was based on the
fact that our institution has both roles, that is as Nuclear Regulatory Body
and Reactor Operator, providing it with a very fluent communication and control
relationships; although, each of these roles are well differentiated and independent
within our institution.
The main activities related to this point were the negotiation of contractual
matters, safeguard issues and managerial activities related to transportation,
security, budget, cost scheduling and public relations with the media.
Above all these activities was the coordination and collaborative efforts performed
between CCHEN and DOE, including Washington DC and Savannah River Site personnel.
A very complex communication network at the United States side and the need
for a clear understanding of documents, resolutions and schedules constituted
a difficult test to undertaken by CCHEN personnel. To overcome parallel initiatives
and to avoid misinterpretations it was decided at CCHEN to operate under a single
general manager, directly supported by a technical manager. The main duties
of the general manager were to interact with the United States side at the various
levels, to report and consult permanently with the Executive Director and Board
of Directors of the CCHEN on decision making issues.
2.1.- Contractual Matters
With respect to the legal framework related to this operation, there were a
number of very subtle considerations which needed a quick acquisition and response
time. The way this was resolved was through an intense communication link between
the General Manager at CCHEN and the United States counterparts. This was also
facilitated by the high level of expertise of DOE and Edlow International Co.
personnel in charge. The issues related to Nuclear Liability and Title Transfer
Location were particularly complex and required of significant efforts of all
the parties involved.
At the end of July 1996, the U. S. Department of Energy and CCHEN signed a
Contract to transfer 28 MTR type fuel elements from La Reina Nuclear Center
to the Savannah River Site in South Carolina. These elements are part of the
first 58 fuel elements used in the RECH-1 reactor.
2.2.- Safeguards
Based on the safeguards agreement between the Republic of Chile and the International
Atomic Energy Agency (Article 92, INFCIRF/476), it was necessary to apply in
the United States safeguards to the spent nuclear material in question. This
nuclear material was under IAEA's control during its entire utilization and
decay period at the RECH-1 reactor.
This was strictly a negotiation process that took place between the IAEA and
the United States proper authorities which arrived to a successful outcome by
August 16, 1996.
2.3.- Other Managerial Matters
Several activities were accomplished to insure the physical protection, arrangements
with Customs both at the Port of San Antonio and Airport in Santiago.
Among the physical protection tasks the very first was the notification to
the highest authorities of the Airport, Port and the Special Police and City
Police Authorities. For this we followed the regulation established in the Supreme
Act N_ 12 of 1995 "Regulations for the Safety Transportation of Radioactive
Material" as well as those defined in the International laws on the subject.
The communication at the highest level of the National Emergency Office and
the Authorities mentioned above was facilitated due to the unique position of
CCHEN within the Government structure. As a result of this, all the planning
and coordination at the various levels was straight forward and expeditious.
From this experience, we learned that a high degree of coordination and brief
but accurate information was needed to provide to the Authorities in charged,
and in this way to guarantee a quick response and to maintain the complete operation
under a rigorous centralized control.
For Custom we proceeded in the same way; that is, a formal letter from our
Executive Director to the General Director of Customs initiated a process and
set up the framework for the follow-up events. All the paperwork and authorizations
to do the "temporary admission" of the shipping cask and equipment,
and also the "re-exportation" of the spent fuel elements, were done
efficiently and in prompt manner. In particular, the operations at the Port
in all aspects were really impecable.
2.4- Public Relations
One important aspect during this operation was the CCHEN's handling of the
media with respect to public reaction to the transportation of nuclear material.
Although the Chilean public in general is not negative to nuclear energy (there
are no nuclear power plants in Chile), the influence of the international Green
Peace organization tends to bias people to overreact to nuclear activities.
In this respect, it was decided at CCHEN to maintain a low profile during the
entire operation and only to inform the public through a formal Press Conference.
This conference was called by CCHEN's authorities by special invitation to well
recognized press media, including TV, Radio and print press, and it took place
al CCHEN's headquarters two days before the shipment. The main reason to do
this was to inform the public and politicians about the character and benefits
of this initiative; as well as of all the safety and security measurements being
taken for the handling and transportation of the spent nuclear fuel.
The result of this press conference was achieved 100% with respect to the proposed
objectives. It was clear to the media that the work of all the parties involved
was thoroughly studied, planned and executed in a serious, detailed and responsible
manner. Moreover, it was emphasized that CCHEN was fully complying with the
Chilean law and the international regulations related to the transport of nuclear
material. Incidentally, it was CCHEN which proposed this same set of laws to
the Chilean Parliament several years ago. After the press conference the reaction
of the Green Peace followers in Chile was practically null, and from then on
the Press was given moderated and controlled access to cover the related news.
3.- Technical Activities
Together with the negotiation and management activities it was necessary to
collect the technical information of the spent fuel elements and to initiate
several technical activities at the RECH-1 research reactor. Among the most
important activities were the gathering of the technical information to fill
out the Appendix A (Agreement Spent Nuclear Fuel Acceptance Criteria) of the
contract between the United States Department of Energy and CCHEN. Other activities
were to prepare the RECH-1 reactor to accept the necessary equipment to transfer
the spent fuel elements from the reactor pool to the shipping cask situated
outside of the reactor building, to write the physical protection plan for loading
and transport the spent fuel elements, the risk prevention plan and the operation
procedures for preparing the RECH-1 reactor for transfer operations. The plans
and procedures were approved by the Nuclear Regulatory Body within CCHEN.
During the meeting with the United States Delegation at the La Reina Nuclear
Center on June 21, 1996 it was agreed that 28 spent fuel elements could be sent
in the first shipment from the RECH-1 reactor to the Savannah River Site. Another
important conclusion was the impossibility to remove or chop off the end-boxes
and/or end-fitting from the fuel elements.
NAC International Inc. provided the necessary equipment for the shipment of
the spent nuclear fuel to the United States. These were the MTR Fuel transfer
System and the NAC LWT shipping cask. To move the heavy materials and facilitate
the operations involved in the loading and transport of the spent fuel elements,
a crane of 50 metric ton of capacity, trucks, forklift and pneumatic scaffoldings
were rented locally.
3.1.- Technical Information of the Spent Nuclear Fuel
The physical and chemical characteristics, approximate isotopic composition,
dimension and weight of the spent nuclear fuel was given in Appendix A of the
Contract as required by the Savannah River Site for the acceptance of the spent
MTR fuel. At RECH-1 reactor the complete history and technical information per
each fuel element is permanently tracked and maintained. This includes manufacturing
specification and drawings and the fuel irradiation history of the fuel elements
which made a straight forward task to fill out the information in Appendix A.
The HEU MTR type fuel elements for the RECH-1 research reactor were fabricated
by the United Kingdom Atomic Energy Authority (UKAEA) at Dounreay, Scotland
in 1973. Each fuel element comprises of sixteen flat plates connected to a lower
spigot fitting and carrying cross-rods in an upper fitting provided for lifting
the element. The fuel plates are composed of enriched uranium (80% U-235) aluminum
alloy sandwiched between the high purity aluminum. The outer plates load a half
of the uranium content of the inner plates. A summary description of the fuel
element and the fuel plate are shown in Tables 1 and 2, respectively.
Based on the irradiation history of each spent fuel element, the additional
information required in Appendix A was determined. Particularly, the following
parameters were evaluated; burnup and the content of Special Nuclear Material
(SNM) after irradiation, period of time that the fuel element stays in core,
irradiation time, cooling time, energy obtained per fuel element, dose rate
at 1 meter in air and decay heat. All of this information is shown in Tables
3 and 4.
3.2.- Reactor Preparation
Another important activity was to prepare the RECH-1 reactor to load the spent
fuel elements into the shipping cask using the NAC's Fuel Transfer System. This
is a dry transfer system and consisting of a transfer cask with MTR fuel basket
grapple, a transfer cask carriage, a cask adapter and a pool adapter. Due to
physical restrictions at the RECH-1 reactor, the transfer cask was used to move
spent fuel from the reactor pool to the shipping cask located right outside
the reactor building.
A complete technical information of the NAC's equipment was received at CCHEN
in advanced. Using this information, the reactor personnel prepared the platform
of the reactor and selected the proper location to install the pool adapter
base to support the pool adapter. The disposition of the pool adapter is shown
in Fig. 1. The platform of the reactor and all working areas were cleared to
prevent accidents and to provide enough space for workers.
To prevent any difficulty during the loading operation, a complete inspection
of the 20 metric ton overhead crane and the air compressor system was done.
The latter one is needed for the pneumatic operation of the cask and tools.
A line of demineralized water was installed for decontamination purposes and
to fill out the cask prior to shipment, with the purpose to take water samples
to verify the Cs-137 concentration acceptable for shipping. Helium was required
for leak testing of the shipping cask closure lid. For this reason, a bottle
of helium was provide at the operation area. Helium was also used to fill the
cask cavity and maintain the fuel elements under an inert atmosphere during
the transport.
In order to have all the 28 spent fuel elements closer to the area where the
fuel baskets were to be loaded, these elements were relocated from their original
storage racks. Reactor personnel fully documented the new set up of the elements.
A temporary platform to support the fuel basket in the reactor pool was also
installed.
The Article V.D. and Appendix B (Agreement Transport Package (Cask) Acceptance
Criteria) of the Contract requires that a water sample of the storage pool be
taken and shipped in accordance with the instructions received from the Savannah
River Site.
Fig. 2 shows the Provisional Cask Loading Diagram with a sketch of the fuel
element positions with identification numbers of the authorized fuel elements.
Fig. 3 illustrates the basket locations in the cask cavity. After the cask was
actually loaded, the Provisional Cask Loading Diagram was replaced by a Definitive
Cask Loading Diagram describing the final arrangement of the elements in the
cask loading. In our case, the Definitive Cask Loading Diagram only confirmed
the provisional one.
3.3.- Loading Operation
On August 2, 1996 the giant Antonov 124 cargo plane arrival in Santiago carrying
an ISO container housing the shipping cask; and the necessary equipment from
the United States. CCHEN's personnel received the material at the airport and
coordinated the 20 Km transportation to La Reina Nuclear Center.
The loading operation was based on the NAC¥s Procedure for the MTR Fuel
Dry Transfer System used in conjunction with a NAC LWT shipping cask. This procedure
provides with the necessary steps to operate the system, assisting the user
to prepare the requirement for the operation and to inform the user with the
operation features of the system. In spite of the details contained in this
operating Procedure, the presence of qualified personnel of NAC International
Inc. was essential to expedite the preparation before and during the loading.
In this sense, the Procedure is meant to be utilized as a guide by experienced
personnel.
After a inspection for damage, the equipment was removed from the boxes on
August 19, 1996 and set up at the designed location. When the lid from the container
was removed, a Health Physics survey of the shipping cask and adjacent surface
of the container were performed.
Once the top and bottom impact limiters from the shipping cask were removed,
the shipping cask was carefully raised to a vertical position on the rear cask
support and lift it to place onto the base plate. The pressure in the cask cavity
was equalized using a vent valve and then the closure lid was removed. Through
visual inspection of the cask cavity, six empty baskets were found into it.
These baskets were removed using the transfer cask and decontamination of the
cask cavity took place.
On August 20, 1996 the written authorization from the DOE to initiate the loading
of the spent nuclear fuel into the shipping cask was received. Thus, on August
21, 1996 the loading operation of 28 spent fuel elements was fully carried out.
During the process loading of each spent fuel element, in accordance to Article
X.E. of the Contract, a description of the observable physical condition was
recorded. The results showed no visual evidence of corrosion, pitting cuts or
any other physical indication of damage of the authorized fuel elements.
The cask cavity was flooded with demineralized water to do radiological contamination
surveys in accordance with the specifications giving in Appendix B. During the
same day, at 19:30 hr the first water sample was taken; followed by a second
sample collected at 08:30 hr of the next day. The average Cs-137 concentration
of 382 Bq/l for the first water sample and 610 Bq/l for the second sample were
registered. The level of activity should be under the value specified in Table
1 of the Appendix B. In the case of NAC LWT shipping cask, the Cs-137 concentration
must to be less than 278 dpm/ml (4,630 Bq/l).
To remove the water from the shipping cask, pressurized air was blown into
the cavity followed by vacuum dried process according to the operating Procedure.
Then, the cask cavity was filled with helium and the closure lid was leak tested.
After accomplishing all the about test, the shipping cask was moved back to
the container and the impact limiters were reinstalled. When the container lid
was installed it was sealed by a IAEA¥s inspector who verified the nuclear
material during the loading. Finally, the health physics surveys and the shipping
documents were completed.
All the associated equipment used in the operation were packed back in the
designated boxes in the same original configuration.
3.4.- Transport to the Port of San Antonio
The last operation was to transport the shipping cask from La Reina Nuclear
Center to the port of San Antonio located about 120 Km from Santiago. The transport
was done by using the highway from Santiago to San Antonio. The route was selected
by the Physical Protection and Risk Prevention Group among other alternatives.
The convoy consisting of the container-truck, transit police cars and vans with
CCHEN and NAC personnel. This convoy was additionally protected by Special Police
Group.
On August 26, 1996 the written authorization from DOE for shipping was received.
The same night the convoy left La Reina Nuclear Center towards San Antonio,
reaching the port after four hours journey. After arrival at port the container-truck
proceeded immediately to the pier where a vessel chartered for this operation
was waiting to pick up the container.
On Sunday, September 22, 1996 the ship arrived at the Charleston Naval Weapons
Station in South Carolina carrying two NAC LWT shipping casks. One from Chile
and the other one from Colombia. The containers were transported by train reaching
Savannah River Site the evening of September 22.
4.- Conclusions
It is essential for the Reactor Operator to identify the different local authorities
who are responsible for the decisions on the diverse issues related to the operation.
In some countries it is conceivable that the decision making process could involve
many Government institutions and/or branches, causing compressible complications
and delays.
It is recommended for the Reactor Operator to have legal advice at their own
Institution and/or at the Ministry of External Affairs.
An important issue is for the Reactor Operator to have a complete understanding
of the rights and obligations pertaining to the original contract of the U.S.
supplied enriched uranium.
Due to the diversity of tasks to undertake by the Reactor Operator we found
essential to work under a centralized and vertical organizational scheme with
a General Manager of the operation supported closely by a Technical Manager
who is responsible for the normal operation of the reactor. It is highly recommended
for both managers to have a capability of communicating with their respective
counterparts in the United States. It is also advisable to identify the Top
Manager of the U.S. counterpart from the beginning of the operation.
It is recommended for the Reactor Operator to have detailed documentation of
the fuel element characteristics, specifications, drawings, irradiation history,
water quality records among others.
It was found that the presence at the reactor site of an experience person from the cask owner company, before and during the operation, was very important. This is to resolve critical technical issues that arise and to facilitate the communication traffic between the parties.
Table 1
(c) Full 'Assembly' Description
Number of subassemblies/elements | 16 (14 inner plates + 2 outer plates) |
Over-all dimensions (cm) | 99.3 x 7.46 x 7.47 |
Over-all weight (g) | 4788 |
Casing Material (Zr, Al, etc.) | ---------- |
Casing dimensions (cm), weight (g) | ---------- |
Side plate material | Aluminum |
Side plate dimensions (cm), weight (g)* | 65.09 x 7.4 x 0.485, 566 |
Spacer material | ---------- |
Spacer dimensions (cm), weight (g) | ---------- |
End box material | Aluminum |
End box dimensions (cm), weight (g) | See draw. RECH-1-80-00 to -03, 544.6 |
Braze or weld material | Aluminum |
Braze or weld dimensions (cm), weight (g) | Accounted in the box weight |
Other structural material in assembly (include dimensions and weight) | ---------- |
*Side plate weight shall account for any slot volume(s).
Do the fuel elements contain Sodium (Na) ? No
Table 2
(a) Fuel 'Element' Description .................................INNER ..................OUTER
Fuel element type (plate, disc, rod, tube, etc.) | Plate | Plate |
Nominal dimensions (include clad and bond, cm) | 62.55 x 7.163 x 0.15 | 65.09 x 7.163 x 0.15 |
Active length of fuel element (cm) | 59.69 | 59.69 |
Nominal total weight of fuel element (g) | 194.0 | 197.7 |
Nominal weight of SNM before irradiation (g) | 13.75 | 6.87 |
Total U (g +- g uncertainty) | 13.75 +- 1.00 | 6.87 +- 0.25 |
U-235 (g +- g uncertainty) | 11.0 0.8 | 5.5 0.2 |
Total Pu (g +- g uncertainty) | ---------- | ---------- |
Pu-239 (g +- g uncertainty) | ---------- | ---------- |
Thorium (g +- g uncertainty) | ---------- | ---------- |
Chemical form of SNM (e.g., UO2, UAlx-alloy, UC, etc.) | UAl-Alloy | UAl-Alloy |
Weight of SNM (g) | ---------- | ---------- |
Fabricated form of SNM (pellets, slugs, ribbons) | ---------- | ---------- |
Alloy or dispersing material (Al, SS, etc.) | Aluminum | Aluminum |
Alloy or dispersing material weight (g) | 41.69 | 43.57 |
Cladding material (Al, SS, etc.) & method of sealing | Aluminum | Aluminum |
Clad thickness (cm), weight (g) | 0.046, 138.6 | 0.046, 147.3 |
Bonding material, if any (Na, Al-Si, etc.) | ---------- | ---------- |
Bond thickness (cm), weight (g) | ---------- | ---------- |
Spacers, inactive material (MgO, SS, etc.) | ---------- | ---------- |
Spacer dimensions (cm), weight (g) | ---------- | ---------- |
Other materials contained in the fuel element:(include dimensions and weights) | ---------- | ---------- |
Table 3. Fuel Irradiation History. General Summary
Unique ID No. |
Total Weight fuel asse. |
Fuel Ass. Loaded on |
Fuel Ass. Discharged on |
Time in Reactor Core |
Irradiation Time |
Cooling Time |
Dose Rate at 1[m] in air |
Decay Heat |
[g] |
dd-mm-yy |
dd-mm-yy |
[days] |
[days] |
[days] |
[rem/h] |
[W] |
|
D561 |
4779 |
18-Mar-81 |
02-Jan-92 |
3934 |
517 |
1699 |
71.0 |
5.38 |
D560 |
4788 |
18-Mar-81 |
02-Jan-92 |
3934 |
517 |
1699 |
72.3 |
5.46 |
D551 |
4781 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
55.4 |
3.26 |
D543 |
4761 |
12-Oct-74 |
02-Jan-89 |
5190 |
683 |
2794 |
55.7 |
3.21 |
D572 |
4766 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
54.9 |
3.22 |
D577 |
4797 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
55.4 |
3.25 |
D526 |
4789 |
09-Oct-74 |
02-Jan-89 |
5193 |
683 |
2794 |
58.5 |
3.36 |
D528 |
4775 |
09-Oct-74 |
02-Jan-89 |
5193 |
683 |
2794 |
55.6 |
3.20 |
D508 |
4779 |
27-Apr-77 |
02-Jan-89 |
4260 |
560 |
2794 |
55.5 |
3.48 |
D534 |
4787 |
29-Apr-75 |
02-Jan-89 |
4988 |
656 |
2794 |
55.3 |
3.24 |
D583 |
4782 |
27-Jan-75 |
02-Jan-89 |
5080 |
668 |
2794 |
57.2 |
3.32 |
D595 |
4744 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
57.7 |
3.39 |
D538 |
4778 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
55.5 |
3.26 |
D545 |
4793 |
31-May-75 |
02-Jan-89 |
4956 |
652 |
2794 |
56.0 |
3.29 |
D549 |
4786 |
31-May-75 |
02-Jan-89 |
3131 |
412 |
2794 |
58.9 |
3.96 |
D576 |
4819 |
27-Jan-75 |
30-Nov-88 |
5048 |
664 |
2826 |
57.0 |
3.30 |
D559 |
4803 |
31-May-75 |
30-Nov-88 |
4924 |
648 |
2826 |
57.7 |
3.39 |
D540 |
4785 |
31-May-75 |
11-Oct-88 |
4875 |
641 |
2875 |
57.5 |
3.37 |
D558 |
4806 |
31-May-75 |
11-Oct-88 |
4875 |
641 |
2875 |
57.1 |
3.35 |
D547 |
4804 |
31-May-75 |
11-Oct-88 |
4875 |
641 |
2875 |
57.1 |
3.34 |
D588 |
4810 |
31-May-75 |
03-Aug-88 |
4807 |
632 |
2948 |
55.5 |
3.25 |
D578 |
4795 |
31-May-75 |
03-Aug-88 |
4807 |
632 |
2948 |
56.4 |
3.30 |
D537 |
4784 |
31-May-75 |
03-Aug-88 |
4807 |
632 |
2948 |
56.2 |
3.29 |
D546 |
4796 |
31-May-75 |
11-May-88 |
4720 |
621 |
3030 |
54.4 |
3.19 |
D536 |
4802 |
31-May-75 |
11-May-88 |
4720 |
621 |
3030 |
53.9 |
3.16 |
D539 |
4785 |
31-May-75 |
11-May-88 |
4720 |
621 |
3030 |
55.8 |
3.26 |
D529 |
4792 |
09-Oct-74 |
11-May-88 |
4957 |
652 |
3030 |
55.4 |
3.19 |
D530 |
4790 |
09-Oct-74 |
02-Dec-87 |
4798 |
631 |
3189 |
54.0 |
3.11 |
Table 4. Fuel Irradiation histroy. Assembly Specific Data.
Assembly | Pre-Irradiation | Post-Irradiation | ||||||||||||
Unique ID No. |
U |
U-235 |
U |
U-235 |
U-236 |
Np-237 |
Pu |
Pu-239 |
Pu-241 |
Time in Reactor |
Cooling Time |
Power Level |
Exposure Burn up |
Decay Heat |
[g] |
[g] |
[g] |
[g] |
[g] |
[g] |
[g] |
[g] |
[g] |
[days] |
[days] |
[MWd/asse.] |
[%] |
[Watt] |
|
D561 |
202,300 |
161,840 |
134,921 |
81,571 |
13,837 |
0.13 |
0.7451 |
0.58 |
0.04 |
3934 |
1699 |
69.5 |
49,598 |
5.38 |
D560 |
202,450 |
161,970 |
134,174 |
80,626 |
14,023 |
0.13 |
0.7453 |
0.58 |
0.04 |
3934 |
1699 |
70.6 |
50,222 |
5.46 |
D551 |
205,850 |
164,680 |
140,337 |
86,705 |
13,448 |
0.11 |
0.7142 |
0.57 |
0.03 |
4956 |
2794 |
70.2 |
47,349 |
3.26 |
D543 |
206,780 |
165,420 |
140,890 |
86,991 |
13,516 |
0.11 |
0.7142 |
0.57 |
0.03 |
5190 |
2794 |
67.9 |
47,412 |
3.21 |
D572 |
203,310 |
162,650 |
138,455 |
85,426 |
13,322 |
0.11 |
0.7142 |
0.57 |
0.03 |
4956 |
2794 |
66.9 |
47,478 |
3.22 |
D577 |
205,990 |
164,790 |
140,501 |
86,843 |
13,439 |
0.11 |
0.7142 |
0.57 |
0.03 |
4956 |
2794 |
68.6 |
47,301 |
3.25 |
D526 |
209,730 |
167,780 |
139,506 |
85,558 |
13,701 |
0.12 |
0.7348 |
0.58 |
0.03 |
5193 |
2794 |
71.4 |
49,006 |
3.36 |
D528 |
206,330 |
165,060 |
140,914 |
86,830 |
13,616 |
0.11 |
0.7142 |
0.57 |
0.03 |
5193 |
2794 |
69.4 |
47,395 |
3.20 |
D508 |
208,000 |
166,400 |
142,324 |
88,224 |
13,474 |
0.11 |
0.7141 |
0.57 |
0.03 |
4260 |
2794 |
67.6 |
46,981 |
3.48 |
D534 |
205,610 |
164,490 |
140,238 |
86,683 |
13,411 |
0.11 |
0.7142 |
0.57 |
0.03 |
4988 |
2794 |
69.7 |
47,302 |
3.24 |
D583 |
204,600 |
163,680 |
136,979 |
83,275 |
13,756 |
0.12 |
0.7348 |
0.58 |
0.03 |
5080 |
2794 |
68.4 |
49,123 |
3.32 |
D595 |
207,840 |
166,270 |
139,706 |
85,168 |
13,981 |
0.12 |
0.7247 |
0.57 |
0.03 |
4956 |
2794 |
72.1 |
48,777 |
3.39 |
D538 |
205,810 |
164,650 |
140,128 |
86,475 |
13,479 |
0.11 |
0.7142 |
0.57 |
0.03 |
4956 |
2794 |
69.2 |
47,479 |
3.26 |
D545 |
206,750 |
165,400 |
140,499 |
86,520 |
13,609 |
0.11 |
0.7143 |
0.57 |
0.03 |
4956 |
2794 |
67.2 |
47,691 |
3.29 |
D549 |
206,910 |
165,530 |
140,471 |
86,285 |
13,721 |
0.12 |
0.7143 |
0.57 |
0.03 |
3131 |
2794 |
69.8 |
47,873 |
3.96 |
D576 |
204,490 |
163,590 |
136,935 |
83,131 |
13,877 |
0.12 |
0.7349 |
0.58 |
0.03 |
5048 |
2826 |
65.6 |
49,183 |
3.30 |
D559 |
205,240 |
164,190 |
136,689 |
82,627 |
14,066 |
0.13 |
0.7451 |
0.58 |
0.03 |
4924 |
2826 |
70.3 |
49,676 |
3.39 |
D540 |
206,960 |
165,570 |
138,084 |
83,627 |
14,122 |
0.12 |
0.7350 |
0.58 |
0.03 |
4875 |
2875 |
70.0 |
49,492 |
3.37 |
D558 |
206,250 |
165,000 |
137,935 |
83,674 |
14,035 |
0.12 |
0.7349 |
0.58 |
0.03 |
4875 |
2875 |
70.9 |
49,288 |
3.35 |
D547 |
205,510 |
164,410 |
137,184 |
83,101 |
14,021 |
0.12 |
0.7350 |
0.58 |
0.03 |
4875 |
2875 |
69.3 |
49,455 |
3.34 |
D588 |
204,500 |
163,600 |
137,101 |
83,411 |
13,810 |
0.12 |
0.7348 |
0.58 |
0.03 |
4807 |
2948 |
67.1 |
49,015 |
3.25 |
D578 |
206,780 |
165,420 |
139,310 |
83,999 |
14,437 |
0.12 |
0.7349 |
0.58 |
0.03 |
4807 |
2948 |
67.0 |
49,221 |
3.30 |
D537 |
205,830 |
164,660 |
137,711 |
83,593 |
13,981 |
0.12 |
0.7349 |
0.58 |
0.03 |
4807 |
2948 |
69.0 |
49,233 |
3.29 |
D546 |
203,750 |
163,000 |
137,961 |
83,261 |
14,649 |
0.12 |
0.7348 |
0.58 |
0.03 |
4720 |
3030 |
70.2 |
48,920 |
3.19 |
D536 |
202,710 |
162,170 |
137,659 |
83,155 |
14,190 |
0.12 |
0.7247 |
0.57 |
0.03 |
4720 |
3030 |
70.8 |
48,724 |
3.16 |
D539 |
206,280 |
165,020 |
138,002 |
83,371 |
14,210 |
0.12 |
0.7350 |
0.58 |
0.03 |
4720 |
3030 |
67.9 |
49,478 |
3.26 |
D529 |
205,500 |
164,400 |
137,441 |
83,085 |
14,146 |
0.12 |
0.7350 |
0.58 |
0.03 |
4957 |
3030 |
70.8 |
49,462 |
3.19 |
D530 |
206,280 |
165,020 |
137,862 |
83,583 |
14,055 |
0.12 |
0.7349 |
0.58 |
0.03 |
4798 |
3189 |
68.8 |
49,350 |
3.11 |