Development of simulation program. SHAWED for analysis of accident of evaporation to dryness by boiling of reprocessed high level liquid waste in tank
Creators
- 1. Japan Atomic Energy Agency, Sector of Nuclear Safety Research and Emergency Preparedness, Nuclear Safety Research Center, Reactor Safety Research Division, Tokai, Ibaraki (Japan)
- 2. Frontier System Co., Ltd., Mito, Ibaraki (Japan)
Description
An accident of evaporation to dryness by boiling of high level liquid waste (HLLW) is postulated as one of the severe accidents at a fuel reprocessing plant. Two major mechanisms are expected for fission products (FPs) transfer from liquid to vapor phase. One is non-volatiles FPs transfer in the form of mists to the vapor phase in the tank, the other is volatilization of such as Ruthenium. These FPs transferred to the vapor phase in the tank could be released with water and nitric-acid mixed steam and NO2 gas flow to the environment. NO2 is generated from denitration of nitrate fission products during dry out phase. These phenomena occurred in this accident originate from the liquid waste boiling in the tank. It is essential for the risk assessment of this accident to simulate thermo-hydraulic and chemical behaviors in the waste tank quantitatively with a versatile computer program. The SHAWED (Simulation of High-level radioActive Waste Evaporation and Dryness) has been developed to realize these requirements. In this report, detailed description of major analytical models is explained based on the features of this accident, and some simulation examples are also described for the use in an actual risk assessment. (author)
Availability note (English)
Also available from JAEA; DOI: https://doi.org/10.11484/jaea-research-2022-011Abstract (Japanese)
再処理施設の過酷事故の一つとして高レベル放射性廃液貯槽の冷却機能喪失による蒸発乾固事故が想定される。再処理廃液の沸騰段階での放射性物質の気相部への移行のメカニズムは、沸騰によって生成される飛沫のうち比較的小さい粒径の液滴のエアロゾル化と、揮発性化学種の温度上昇に伴う気化である。気相に移行した放射性物質は、沸騰により発生する硝酸-水混合蒸気や硝酸塩の熱分解による脱硝反応で生じるNO2などとともに貯槽から流出し、施設内を移行し一部は施設外に放出されると想定される。当該事故で生じるこれらの諸事象は、すべて貯槽内の廃液の沸騰を起源とするため、それによって生じるリスクを精度良く評価するには、汎用性のある計算プログラムを用いた貯槽内の熱水力的及び化学的挙動の定量的な模擬が不可欠である。これを目的として再処理廃液の沸騰を模擬する計算プログラム: SHAWED (Simulation of High-level radioActive Waste Evaporation and Dryness)を開発した。本報では、当該事故のリスク評価に資するために、模擬対象とする事象の特徴をもとに沸騰及びそれに伴う諸事象の模擬に必要な主要な解析モデルを説明するとともに、具体的な模擬事例を示す。(著者)
Files
Additional details
Additional titles
- Original title (Japanese)
- 再処理施設の高レベル廃液貯槽蒸発乾固事故解析のための廃液沸騰模擬計算プログラム.SHAWEDの整備
Identifiers
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- JAEA-Research--2022-011
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54086967
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BOILING; DENITRATION; EVAPORATION; FISSION PRODUCTS; FUEL REPROCESSING PLANTS; HIGH-LEVEL RADIOACTIVE WASTES; LIQUID WASTES; RADIOACTIVE AEROSOLS; RISK ASSESSMENT; S CODES; SEVERE ACCIDENTS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; AEROSOLS; BEYOND-DESIGN-BASIS ACCIDENTS; CHEMICAL REACTIONS; COLLOIDS; COMPUTER CODES; DISPERSIONS; FLUID MECHANICS; HYDRAULICS; ISOTOPES; MATERIALS; MECHANICS; NUCLEAR FACILITIES; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SOLS; WASTES
Optional Information
- Notes
- 27 refs., 31 figs., 3 tabs.