Channel WORM C-14 now off the air.

We come to the end of another irregularly scheduled broadcast.

Viewer comments are always welcome, on all threads. We hope these thoughts instantly go up, for the benefit of insomniacs and night owls. Those needing approval will receive at the start of our next broadcast.

Some aspects of the Fukushima crisis gradually clarify. But conflicting and troubling information also mounts, from as far as 40 kilometers away. There remains no indication of danger to anyone beyond Nippon’s shores.

We will of course notify you, our viewers, of noteworthy changes immediately upon learning them.

We pray for the victims in Japan, where our thoughts have focused in recent days. But we pray also for all others in great need, whose want is no less because of our ignorance.

And now, tents now pitched in Weslaco TX, we turn our eyes skyward. By the contrails of jets and the majesty of the Anthem, we bid this treasured community goodnight:

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About wormme

I've accepted that all of you are socially superior to me. But no pretending that any of you are rational.
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6 Responses to Channel WORM C-14 now off the air.

  1. oldHP says:

    Anybody have access to this journal? Might show the valve lineup for seawater injection:

    http://www.sciencedirect.com/science?_ob=ArticleURL&_udi=B6V4D-47XN3BW-73&_user=10&_coverDate=01%2F01%2F1989&_rdoc=1&_fmt=high&_orig=gateway&_origin=gateway&_sort=d&_docanchor=&view=c&_searchStrId=1691533594&_rerunOrigin=google&_acct=C000050221&_version=1&_urlVersion=0&_userid=10&md5=038c7a4174b0249367da5843c500b7cf&searchtype=a

    Nuclear Engineering and Design
    Volume 110, Issue 3, 1 January 1989, Pages 385-393

    A post trip operational guidance system for BWR plants

    Purchase
    $ 31.50
    Yoji Takizawaa, Toshifumi Hayashia, Nobuyuki Saijoua and Toshihiko Moriokab
    aNippon Atomic Industry Group Co., Ltd., 4-1, Ukishima-cho, Kawasaki-ku, Kawasaki-shi, 210 Japan
    bIsogo Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama-shi, 235 Japan
    Received 22 December 1987. Available online 14 February 2003.
    Abstract
    A post trip operational guidance system (PTOG) for BWR power plants was developed to support the operators in achieving safe plant shutdown after a scram. The objective of PTOG is to support the operators in collecting plant information, in diagnosing plant status and in deciding corrective actions. To achieve this objective, PTOG has three main functions, i.e., the diagnosis of plant subsystems performance, the identification of safety functions status and the dynamic synthesis of operating procedures. The main advantage of PTOG is that it provides operating procedures irrespective of the transient’s initiating event and evolutional history. The results of verification and validation tests showed that PTOG was a useful, effective and trustworthy vehicle in coping with abnormal plant conditions.

  2. oldHP says:

    Nice color schematic here, but with suppression pool instead of torus:

  3. oldHP says:

    Wish I had found this site days ago. Great stuff, well organized.

    This as of Mar 16th:

    http://www.world-nuclear-news.org/RS_Second_fire_reported_at_unit_4_1603111.html

    The peak of radiation on site is near unit 3, where levels of 400 millisieverts per hour have been recorded. Dose limits to workers under emergency regulations have been raised to 250 millisieverts from 100 millisieverts after which they may not return. This compares to usual nuclear worker limits of 20 millisieverts per year.

    ***
    So they are letting workers take 25 rems. I suppose the 50 Heroes are taking more.

  4. oldHP says:

    PRIMARY SOURCE MATERIAL

    TEPCO press releases; start with # 169

    http://www.tepco.co.jp/en/press/corp-com/release/

  5. oldHP says:

    FIRST BODY SHOP ON THE SCENE

    http://www.nukeworker.com/job/view.php?job_id=14254

    “contract in place”
    “salary & per diem to be negotiated”

  6. oldHP says:

    WAYS FOR PUMPS TO FAIL:

    Everything you always wanted to know about debris:

    http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7011/cr7011.pdf

    NUREG/CR-7011
    PNNL-17972

    Evaluation of Treatment of
    Effects of Debris in Coolant on
    ECCS and CSS Performance in
    Pressurized Water Reactors and
    Boiling Water Reactors

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