Study of annual tritium discharge in pressurized water reactor based on historical data

Pengtao Fu; Mingliang Dai; Zhaowen Zhu; Xinhua Liu; Lan Fang; Chunyan Xu

doi:10.11884/HPLPB202234.210399

Journals >High Power Laser and Particle Beams >Volume 34 >Issue 2 >Page 026009 > Article

High Power Laser and Particle Beams
Vol. 34, Issue 2, 026009 (2022)

Study of annual tritium discharge in pressurized water reactor based on historical data

Pengtao Fu¹, Mingliang Dai¹, Zhaowen Zhu², Xinhua Liu², Lan Fang², and Chunyan Xu²

Author Affiliations

¹China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China

²Nuclear and Radiation Safety Center，Ministry of Ecology and Environment，Beijing 100082, China

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DOI: 10.11884/HPLPB202234.210399 Cite this Article

Pengtao Fu, Mingliang Dai, Zhaowen Zhu, Xinhua Liu, Lan Fang, Chunyan Xu. Study of annual tritium discharge in pressurized water reactor based on historical data[J]. High Power Laser and Particle Beams, 2022, 34(2): 026009 Copy Citation Text

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Fig. 1. Quarter reactor JMCT model

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Fig. 2. Comparison between calculated and measured values of tritium production by neutron activation

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Fig. 3. Comparison between calculated and measured values of tritium production (1% released from fuel)

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Fig. 4. Comparison between calculated and measured values of tritium production of Daya Bay Nuclear Power Plant

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Fig. 5. Schematic diagram of SNS in double-layer stainless steel cladding

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Fig. 6. Variation of tritium discharge from French 900 MWe PWR

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region	nuclear reaction
fuel	$ {\text{U/Pu}} + {}_0^1{\text{n}}\xrightarrow{{}}{\text{FP1 + FP2}} + {}_1^3{\text{H}} $
boric acid（primary coolant）	$ {}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{({\text{n,2α}} )}}}{\text{2}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}} $$ {}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,nα )}}}}{}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{2}}^{\text{4}}{\text{He}} $ ⇨ $ {}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}} $$ {}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{2}}^{\text{4}}{\text{He}} $ ⇨ $ {}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $
boric acid（primary coolant）	$ {}_{\text{5}}^{{\text{11}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ ⇨ $ {}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{2}}^{\text{6}}{\text{He}} $⇨ $ {}_{\text{2}}^{\text{6}}{\text{He}}\xrightarrow{{\text{β }}}{}_{\text{3}}^{\text{6}}{\text{Li + }}_{ - 1}^{\text{0}}{\text{e}} $ ⇨ $ {}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}} $$ {}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ ⇨ $ {}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $
lithium hydroxide（primary coolant）	$ {}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}} $$ {}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $
deuterium（primary coolant）	$ {}_{\text{1}}^{\text{2}}{\text{H + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,γ )}}}}{}_{\text{1}}^{\text{3}}{\text{H}} $
antimony-beryllium in SNS	$ {}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{2}}^{\text{6}}{\text{He}} $ ⇨ $ {}_{\text{2}}^{\text{6}}{\text{He}}\xrightarrow{{\text{β }}}{}_{\text{3}}^{\text{6}}{\text{Li}} $ ⇨ $ {}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}} $$ {}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ ⇨ $ {}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $

Table 1. Nuclear reaction of tritium production in PWR

origin	relative contribution/%
origin	EPR	AP1000	VVER
fuel	0	31	22
boric acid and lithium hydroxide	83	69	77
SNS	17	0	−
total	100	100	100

Table 2. Relative contribution of expected tritium production in different reactor

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