Abstract
Fission product release from overheated fuel is one of the key phenomena controlling the source terms in hypothetical severe accidents. In-pile and out-of-pile heating tests of the fuel have been conducted to study the release behavior in the world. In-pile tests covered a wide range of accident conditions up to fuel melting under high pressure. The uncertainty and variation of the test conditions in the in-pile test, however, made the interpretation very difficult. The out-of-pile tests under better controlled conditions, on the other hand, was limited below 2425degC under the atmospheric pressure. Thus, considerable uncertainties still remain, especially in the areas under high temperature and/or high pressure conditions. An experimental and analytical program, Verification Experiment of Gas/Aerosol release (VEGA), was initiated at JAERI to study the fission product release behavior from light water reactor fuels irradiated in Japanese power reactors. A short fuel segment will be inductively heated to high temperatures in a hot cell under simulated accident conditions. In the program, less understood release and transport behavior of low volatile and short life fission products will be studied, 1. under high temperature conditions, covering melting temperature of the fuel, and, 2. at high pressure conditions up to 1.0 MPa.
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Nakamura, Takehiko;
Hidaka, Akihide;
Hashimoto, Kazuichiro;
Harada, Yuhei;
Nishino, Yasuharu;
Kanazawa, Hiroyuki;
Uetsuka, Hiroshi;
Sugimoto, Jun
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Nakamura, Takehiko, Hidaka, Akihide, Hashimoto, Kazuichiro, Harada, Yuhei, Nishino, Yasuharu, Kanazawa, Hiroyuki, Uetsuka, Hiroshi, and Sugimoto, Jun.
Research program (VEGA) on the fission product release from irradiated fuel.
Japan: N. p.,
1999.
Web.
Nakamura, Takehiko, Hidaka, Akihide, Hashimoto, Kazuichiro, Harada, Yuhei, Nishino, Yasuharu, Kanazawa, Hiroyuki, Uetsuka, Hiroshi, & Sugimoto, Jun.
Research program (VEGA) on the fission product release from irradiated fuel.
Japan.
Nakamura, Takehiko, Hidaka, Akihide, Hashimoto, Kazuichiro, Harada, Yuhei, Nishino, Yasuharu, Kanazawa, Hiroyuki, Uetsuka, Hiroshi, and Sugimoto, Jun.
1999.
"Research program (VEGA) on the fission product release from irradiated fuel."
Japan.
@misc{etde_10147601,
title = {Research program (VEGA) on the fission product release from irradiated fuel}
author = {Nakamura, Takehiko, Hidaka, Akihide, Hashimoto, Kazuichiro, Harada, Yuhei, Nishino, Yasuharu, Kanazawa, Hiroyuki, Uetsuka, Hiroshi, and Sugimoto, Jun}
abstractNote = {Fission product release from overheated fuel is one of the key phenomena controlling the source terms in hypothetical severe accidents. In-pile and out-of-pile heating tests of the fuel have been conducted to study the release behavior in the world. In-pile tests covered a wide range of accident conditions up to fuel melting under high pressure. The uncertainty and variation of the test conditions in the in-pile test, however, made the interpretation very difficult. The out-of-pile tests under better controlled conditions, on the other hand, was limited below 2425degC under the atmospheric pressure. Thus, considerable uncertainties still remain, especially in the areas under high temperature and/or high pressure conditions. An experimental and analytical program, Verification Experiment of Gas/Aerosol release (VEGA), was initiated at JAERI to study the fission product release behavior from light water reactor fuels irradiated in Japanese power reactors. A short fuel segment will be inductively heated to high temperatures in a hot cell under simulated accident conditions. In the program, less understood release and transport behavior of low volatile and short life fission products will be studied, 1. under high temperature conditions, covering melting temperature of the fuel, and, 2. at high pressure conditions up to 1.0 MPa. The program will be carried out keeping a close corporation with the NSRR RIA program, sharing the test fuel specimens and examination results. This way, irradiated fuel behavior and characteristics under various accident conditions are studied comprehensively. This report describes background, status and outlines of the VEGA program. (author)}
place = {Japan}
year = {1999}
month = {Mar}
}
title = {Research program (VEGA) on the fission product release from irradiated fuel}
author = {Nakamura, Takehiko, Hidaka, Akihide, Hashimoto, Kazuichiro, Harada, Yuhei, Nishino, Yasuharu, Kanazawa, Hiroyuki, Uetsuka, Hiroshi, and Sugimoto, Jun}
abstractNote = {Fission product release from overheated fuel is one of the key phenomena controlling the source terms in hypothetical severe accidents. In-pile and out-of-pile heating tests of the fuel have been conducted to study the release behavior in the world. In-pile tests covered a wide range of accident conditions up to fuel melting under high pressure. The uncertainty and variation of the test conditions in the in-pile test, however, made the interpretation very difficult. The out-of-pile tests under better controlled conditions, on the other hand, was limited below 2425degC under the atmospheric pressure. Thus, considerable uncertainties still remain, especially in the areas under high temperature and/or high pressure conditions. An experimental and analytical program, Verification Experiment of Gas/Aerosol release (VEGA), was initiated at JAERI to study the fission product release behavior from light water reactor fuels irradiated in Japanese power reactors. A short fuel segment will be inductively heated to high temperatures in a hot cell under simulated accident conditions. In the program, less understood release and transport behavior of low volatile and short life fission products will be studied, 1. under high temperature conditions, covering melting temperature of the fuel, and, 2. at high pressure conditions up to 1.0 MPa. The program will be carried out keeping a close corporation with the NSRR RIA program, sharing the test fuel specimens and examination results. This way, irradiated fuel behavior and characteristics under various accident conditions are studied comprehensively. This report describes background, status and outlines of the VEGA program. (author)}
place = {Japan}
year = {1999}
month = {Mar}
}