ML11214A091: Difference between revisions

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{{#Wiki_filter:* USGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 July 27, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555  
{{#Wiki_filter:* USGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 July 27, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555


==Reference:==
==Reference:==
 
U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010
U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010  


==Subject:==
==Subject:==
Response to Question 2 of the Referenced RAI Mr. Wertz: Question 2: NUREG-1 537, Part 1 Section 4.2. 1, "Reactor Fuel", requests a description of the reactor fuel that includes the material properties.
Response to Question 2 of the Referenced RAI Mr. Wertz:
The GSTR SAR Table 4.1 describes the GSTR fuel inventory as having 8.5 weight percent (wt%) and 12 wt% SS clad fuel and 8 wt% Aluminum clad fuel. However, GSTR SAR subsection 4.2.1.7 only describes the volumetric-specific heat for the 8.5 wt% and 20 wt%fuel. Please provide the volumetric heat capacity for 8 wt% and 12 wt% fuel.Response:
Question 2: NUREG-1 537, Part 1 Section 4.2. 1, "Reactor Fuel", requests a description of the reactor fuel that includes the material properties. The GSTR SAR Table 4.1 describes the GSTR fuel inventory as having 8.5 weight percent (wt%) and 12 wt% SS clad fuel and 8 wt% Aluminum clad fuel. However, GSTR SAR subsection 4.2.1.7 only describes the volumetric-specific heat for the 8.5 wt% and 20 wt%
According to NUREG-1282, "The performance of uranium-zirconium hydride fuel is substantially independent of uranium content up to 45 wt% uranium." The volumetric heat capacity is described by CP = 2.04 + 4.17 *10A3 (T) (W-sec/cm^3-°C).
fuel. Please provide the volumetric heat capacity for 8 wt% and 12 wt% fuel.
Therefore, the volumetric heat capacities for the 8 wt% and 12 wt% fuels are the same as for the 8.5 wt%fuel.
Response: According to NUREG-1282, "The performance of uranium-zirconium hydride fuel is substantially independent of uranium content up to 45 wt% uranium." The volumetric heat capacity is described by CP   = 2.04 + 4.17 *10A3 (T) (W-sec/cm^3-°C).
Therefore, the volumetric heat capacities for the 8 wt% and 12 wt% fuels are the same as for the 8.5 wt%
fuel.


==REFERENCE:==
==REFERENCE:==


M. T. Simnad, "The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel," Nuclear Engineering and Design 64 (November 1980), 403-422.NUREG-1282, op. cit.Our need for outside assistance to answer the detailed, technical RAI questions is being addressed by a DOE contract with the Colorado School of Mines (CSM). The work under this contract is in progress with the development of a detailed MCNP core model and RELAP thermal hydraulics model. An on-site meeting was held on July 19-20 with two representatives from the Oregon State University (OSU)TRIGA facility to discuss proper modeling techniques and methodology for addressing RAI questions.
M. T. Simnad, "The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel," Nuclear Engineering and Design 64 (November 1980), 403-422.
This meeting was very helpful and productive.
NUREG-1282, op. cit.
The OSU representatives told us that they would be available to answer future questions by phone or email.Sincerely, USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct.Executed on 7/27/11 Copy to: Betty Adrian, Reactor Administrator, MS 975}}
Our need for outside assistance to answer the detailed, technical RAI questions is being addressed by a DOE contract with the Colorado School of Mines (CSM). The work under this contract is in progress with the development of a detailed MCNP core model and RELAP thermal hydraulics model. An on-site meeting was held on July 19-20 with two representatives from the Oregon State University (OSU)
TRIGA facility to discuss proper modeling techniques and methodology for addressing RAI questions.
 
This meeting was very helpful and productive. The OSU representatives told us that they would be available to answer future questions by phone or email.
Sincerely, USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct.
Executed on 7/27/11 Copy to:
Betty Adrian, Reactor Administrator, MS 975}}

Latest revision as of 17:46, 12 November 2019

Response to Question 2 of the Referenced RAI
ML11214A091
Person / Time
Site: U.S. Geological Survey
Issue date: 07/27/2011
From: Timothy Debey
US Dept of Interior, Geological Survey (USGS)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11214A091 (2)
v • d • e


Text

  • USGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 July 27, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010

Subject:

Response to Question 2 of the Referenced RAI Mr. Wertz:

Question 2: NUREG-1 537, Part 1 Section 4.2. 1, "Reactor Fuel", requests a description of the reactor fuel that includes the material properties. The GSTR SAR Table 4.1 describes the GSTR fuel inventory as having 8.5 weight percent (wt%) and 12 wt% SS clad fuel and 8 wt% Aluminum clad fuel. However, GSTR SAR subsection 4.2.1.7 only describes the volumetric-specific heat for the 8.5 wt% and 20 wt%

fuel. Please provide the volumetric heat capacity for 8 wt% and 12 wt% fuel.

Response: According to NUREG-1282, "The performance of uranium-zirconium hydride fuel is substantially independent of uranium content up to 45 wt% uranium." The volumetric heat capacity is described by CP = 2.04 + 4.17 *10A3 (T) (W-sec/cm^3-°C).

Therefore, the volumetric heat capacities for the 8 wt% and 12 wt% fuels are the same as for the 8.5 wt%

fuel.

REFERENCE:

M. T. Simnad, "The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel," Nuclear Engineering and Design 64 (November 1980), 403-422.

NUREG-1282, op. cit.

Our need for outside assistance to answer the detailed, technical RAI questions is being addressed by a DOE contract with the Colorado School of Mines (CSM). The work under this contract is in progress with the development of a detailed MCNP core model and RELAP thermal hydraulics model. An on-site meeting was held on July 19-20 with two representatives from the Oregon State University (OSU)

TRIGA facility to discuss proper modeling techniques and methodology for addressing RAI questions.

This meeting was very helpful and productive. The OSU representatives told us that they would be available to answer future questions by phone or email.

Sincerely, USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct.

Executed on 7/27/11 Copy to:

Betty Adrian, Reactor Administrator, MS 975

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