ML20058J679

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Annealing of Housing USA Overview Jcccnrs Working Group 3. Missing Page 1
ML20058J679
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Issue date: 06/07/1989
From: Serpan C
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
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JCCCNRS-WG-3, WG-3.16, NUDOCS 9012020150
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i JCCCNRS Working Group 3.2 Annealing of the Housing, USA Overview 4 Historical Background Annealing of irradiated steel specimens from reactor vessels has been performed in USA research since the late 1950's, when intense research began on the entire topic of radiation induced embrittlement. The important achievement of this early work was_ to show that the recovery of pre-service mechanical properties of irradiated pressure vessels was feasible. The work also showed trends for how much recovery could be expected for different times and tempera- -tures of heat treatment. While enormous strides have since been made in the -technology of annealing, these early results showed the direction that we still follow today. The annealing research sponsored by NRC (and the predecessor research sponsored by the USAEC) as well as that sponsored by US industry has all been done using laboratory test specimens. While no single commercial US reactor has yet been

annealed, one US reactor under control of the Army and located at an Alaskan base for space heat and electricity generation, was in fact annealed in the

. late 1960's. 'The operating-temperature of that plant was sufficiently low that it still cculd operate et,a high enough temperature to_cause an effective-recovery of properties, while also remaining in' vessel code design limits. This SM-1A reactor annealing was done using simple nuclear heat. It is clear that no large conunercial reactor currently in service will be able to effect adequate recovery except by application of heat from supplemental heaters. Recovery and Reernbrittlement Trends A number of primary factors controlling annealing have been determined; these will be discussed in more detail in subsequent presentations. These factors include:

1) Tirre - A large fraction of annealing is ef fected in the first 24 hcors. but a full week appears to be a reasonable optimum; 2) Temperature -

At least 150 to 200'F (75 to 100'C) above the irradiation temperature is needed for recovery, and temperatures above about 850*f appear to recover virtually all en,brittlement; 3) frequency - Annealings done more frequently appear to maintain the overall embrittlement at lower levels. Furthermore, anneeling done earlier in a life will result in a lower overall level of embrittlement; 4) Fluence - Directly tied to frequency, so the earlier the better; 5) Composition - Copper, for example, appears to cause a substantial residual level of embrittlement after annealing; other elements and combina-tions have different effects. Ay11 cation and System Considerations - Experience Studies have been done both by NRC and by the US industry to evaluate the systems considerations and problems that could arise as a result of conducting an annealing. Some of the issues include the following: 1)TypeofHeating-The most likely and most easily controlled is electrical resistance heaters placed adjacent to the vessel wall to be heat treated; 2) Differential stresses and defonnation - Application of the heat to just the vessel beltline can cause significant stresses bctween the very hot and the colder parts of the vessel. This can cause abnormal stresses and growth in unexpected directions which could result in flange and gasket groove warpage, es well as other deformation;

3) Verification of Annealing - Some means must be established to assure that the applied heat has removed the desired embrittlement. There can include indirect n'eans, through test of surveillance specimens located in the vessel i

during the anneal, or through direct nicasurement of the material of the vessel, possibly even through destructive test methods; 4) Code Rules - Because annealings are expected to be done at teriperatures far exceeding their code design allowable limits, provision must be made for consideration of the effect of the heating on the materials other than just the removal of embrittlen<rt so as to maintain proper material and fabrication code acceptance; 5) Experience - No commercial US power reactor has yet been annealed, so experience from annealings of this scale is not available. However, annealing of the Anny SM-1A reactor has been performed, as described briefly above. ?

Conclusions Research work in laboratories, engineering studies conducted by both the NRC and industry, and the evidence of a successful anneal of the SM-1A all lead us to believe that annealing is feasible for recovery of mechanical properties, including toughness. It would be desirable, if not necessary, for an applicant to demonstrate the extent of annealing that actually took place. l l l l l l 3 i

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