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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210G6971999-07-30030 July 1999
Proposed Tech Specs Page 3-39,correcting Typo in Basis Re Storage & Handling of Fuel
ML20209C9231999-07-0808 July 1999
Rev 0,Vol 1 to Proposed TS for Ma Institute of Technology Nuclear Research Lab (MITR-III),in Support of Application for Renewal of License R-37
ML20207E4591999-05-27027 May 1999
Proposed Tech Spec Page 3-39,changing Basis of TS 3.10 to Add Item 3e to Second Line of Second Paragraph & Second Sentence of Fourth Paragraph Changed to Read as Listed
ML20199H2661998-12-31031 December 1998
Revised Proposed Tech Specs Pages Re 971003 Request for Amend to License R-37 & NRC RAI
ML20217G2251997-10-0303 October 1997
Proposed Tech Specs 6.6 Pertaining to Design & Operation of Fission Converter & TS & Minor Changes to Existing TS Necessitated by Adoption of TS 6.6
ML20126M5741992-12-30030 December 1992
Proposed Tech Spec 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20126D8371992-12-22022 December 1992
Proposed TS Section 6.5, Generation of Medical Therapy Facility Beam for Human Therapy & Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20106B2731992-09-23023 September 1992
Proposed TS 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7261992-07-30030 July 1992
Proposed TS 6.5 Re Generation of Medical Therapy Facility Beam for Human Therapy
ML20235J0761989-02-13013 February 1989
Proposed Tech Spec Changes Revising Fission Density Limit & Amending Percentage of Voids Permitted in UA1(x) Type Fuel
ML20112J1961985-01-15015 January 1985
Proposed Tech Spec Changes Re Variable Reactivity & Shutdown Margin & Closed Loop Control Sys
ML20079J9371982-12-22022 December 1982
Proposed Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys.Sar Page 6.6 Re Tests & Surveillance Encl
ML20042B9301982-03-22022 March 1982
Draft Revised Tech Spec 5.2-1 Re Design of Reactor Core
ML19345H4201981-05-14014 May 1981
Proposed Changes to Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage
1999-07-08
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210G6971999-07-30030 July 1999
Proposed Tech Specs Page 3-39,correcting Typo in Basis Re Storage & Handling of Fuel
ML20209C9151999-07-0808 July 1999
Mitr Requalification Program, as Currently Approved & in Effect
ML20209C9231999-07-0808 July 1999
Rev 0,Vol 1 to Proposed TS for Ma Institute of Technology Nuclear Research Lab (MITR-III),in Support of Application for Renewal of License R-37
ML20207E4591999-05-27027 May 1999
Proposed Tech Spec Page 3-39,changing Basis of TS 3.10 to Add Item 3e to Second Line of Second Paragraph & Second Sentence of Fourth Paragraph Changed to Read as Listed
ML20199H2661998-12-31031 December 1998
Revised Proposed Tech Specs Pages Re 971003 Request for Amend to License R-37 & NRC RAI
ML20217G2251997-10-0303 October 1997
Proposed Tech Specs 6.6 Pertaining to Design & Operation of Fission Converter & TS & Minor Changes to Existing TS Necessitated by Adoption of TS 6.6
ML20044G5441993-05-28028 May 1993
Procedures for Conduct of Human Irradiations W/Mit Medical Therapy Facility.
ML20126M5791992-12-30030 December 1992
Revised Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20126M5741992-12-30030 December 1992
Proposed Tech Spec 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20126D8371992-12-22022 December 1992
Proposed TS Section 6.5, Generation of Medical Therapy Facility Beam for Human Therapy & Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20106B2731992-09-23023 September 1992
Proposed TS 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7261992-07-30030 July 1992
Proposed TS 6.5 Re Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7271992-03-0606 March 1992
Quality Mgt Program for Generation of Medical Therapy Facility Beam for Human Therapy at Mit
ML20235J0761989-02-13013 February 1989
Proposed Tech Spec Changes Revising Fission Density Limit & Amending Percentage of Voids Permitted in UA1(x) Type Fuel
ML20112J1961985-01-15015 January 1985
Proposed Tech Spec Changes Re Variable Reactivity & Shutdown Margin & Closed Loop Control Sys
ML20079J9371982-12-22022 December 1982
Proposed Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys.Sar Page 6.6 Re Tests & Surveillance Encl
ML20042B9301982-03-22022 March 1982
Draft Revised Tech Spec 5.2-1 Re Design of Reactor Core
ML19345H4201981-05-14014 May 1981
Proposed Changes to Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage
ML20073H1411978-12-26026 December 1978
Procedure PM 7.4.4.2, ISI of Primary Core Tank & Fuel
1999-07-08
[Table view] |
Text
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- g'4 . .
5.2 Reactor Core Applicability This specification applies to the design of the reactor core.
Obiective To assure compatibility of the reactor core with the present safety analysis.
Specifications -
- 1. The reactor core may consist of up to 27 fuel elements approxf.-
mately 2-3/8" on a' side. The fuel shall be plates of uranium in the form of UAl alloy or UA1 with a maximum of 50 w/o urani'um in the. fuel matrix clad by a layer of aluminum metal incorporating fins on the surface that enhance the heat transfer and having a nominal clad thickness of 0.015 inches at the base of the groove between the fins.
- 2. Design of in-core sample assemblies shall conform to the following criteria: .
- a. they shall be positively secured in the core to prevent movement during reactor operation,
- b. materials of construction shall be radiation resistant and co=patible with those used in the reactor core and primary
' coolant system,
- c. sufficient cooling shall be provided to insure structural integrity of the asse=bly and to preclude any boiling of sthe primary coolant,
, d. the size of the irradiation thimble shall be less than 16 square inches in cross section.
Basis The thermal design analysis in the SAR and the power distributions on which the analysis was based assumed fuel elements of the type specified 8203260300 820322 PDR ADOCK 05000020 5-3 P PDR
- + .
in item 1. Any change in this design would requ. ire re-evaluation of the heat transfer and flow characteristics of the element.
The nominal clad thickness of 0.015" is based upon ctandard practice for MTR type elements with clad of similar thickness. Reference 5.2-1 states (p.148) that the release of radioactive fission ga's to the primary cooling water appears to be adequately prevented by cladding of uniform thickness (>0.2 mm, >0.008 in). This corresponds to the minimum nominal cladding permitted for ATR fuel, where the term " uniform" implies'a provision .
for minor manufacturing deviations (e.g. scratches, indentations, et,c.) from the uniform thickness. Ref. 5.2-2, (p. 672) shows that a thick clad increases the delay time for heat removal in event of' a fast transient. Therefore, the clad should be as thin as possible while still' re=aining compatible with fission product retention requirements.
In-core sample assemblies which satisfy Specification 2a cannot be credibly ejected during operation and are therefore considered part of the reactor structure.
Specification 2b and 2c insure the structural integrity of the assembly and prevent che=ical interactions with the core and primary coolant system.
Specification 2d limits the size of the irradiation area as required by 10 CFR 50.2(r).
References Ref. 5.2-1 Beeston, J.M., R.R. Hobbins, G.W. Gibson, and W.F. Francis,
" Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors", Nuclear Technology, Vol. 49 p. 136-149 (June 1980).
Ref. 5.2-2 Thompson, T.J., and J.G. Beckerly (eds,), The Technology of Nuclear Reactor Safety,.Vol. I, the MIT Press, Camb. MA (1964).
5-4
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